ML20094M059
| ML20094M059 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 09/30/1995 |
| From: | STEVENSON & ASSOCIATES |
| To: | |
| Shared Package | |
| ML20094M035 | List: |
| References | |
| REF-GTECI-A-46, REF-GTECI-SC, TASK-A-46, TASK-OR NUDOCS 9511210252 | |
| Download: ML20094M059 (400) | |
Text
{{#Wiki_filter:- - - - - - - _ _ O New York PowerAuthority James A. FitzPatrick Nuclear Power Plant USl A-46 Seismic Evaluation Report September 1995 NEW YORK POWER AUTHORITY DOCUMENT REVIEW STATUS . SLAJUS N0; 1 )( ACCEPTED R U AL NO REQUIRED R U L R QU RED 4 O NOT ACCEPTED ti atas, anaIm wsi nethoos a mawws cwoped a in, no em not m e nom u anc.nc. um WWED BYkM TITLE:IS .PU I # f'A L ppgpgggd gy orin: JoD7l4F Stevenson & Associates 10 State Street Woburn, Mass. 01801 617-932-9580 C..
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- c. Table of Contents U l
- 1. I n t ro d u c ti o n . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
1.1 Purpose .. . .. . . . . . ....... .. . . . . . . .. . .. .2 1.2 Background... . ... . . . . . . . . .. . .2 1.3 Report Organization . .. .. . . . . .. .. . . . . . .. . . . . .2 , 1.4 Peer Review.... . . . . . . . . . .... . .. .. . . . . . .2 l
- 2. S ei s mi c Desi g n Ba si s . . .. . . . ... . . . . . .. . . . ... . . . . . .. . . . . . . . . . . . . . . . .. . .... .... .. . . . . . . .... . . . . . . . . . ... . . . . . . .... . . . . 3 2.1 Ground Response Spectrum. . . . . . . . ... . . . . . . . . . . . .. 3 2.2 in-structure Response Spectra. .. . . . . . . . . . . .. ... .3 2.3 Grade Elevation .. . . . . . . . . . . . . . . . . . . . . . . . . . . .4
- 3. Mechanical and Electrical Equipment Review....................................................... 5 3.1 Summary of the Review. . . . . . . . ... . . ... .. .5 3.2 Instances of Intent but not Letter of Caveat Met.. . . . . . .. .14 3.3 Summary of Outliers . . . . . . . . . . . . . . . . .18 ]
3.4 Seismic Demand for Essential Relay Cabinets .. ... .. . . . . . . .27 l 1
- 4. Tan ks an d H eat Exch an gers Review.................................................................... 29 4.1 Summary of the Review. . . . . . . . . . . .29 4.2 Summary of Outliers . ... . . . . . . . . . . . . .34
( 5. Cable an d Con duit Raceway Review.................................................................... 35 5.1 Summary of the Review. .. . . . . . . . . . . .35 5.2 Scope of the Review. . .. . .. . . . . . .35 5.3 Limited Analytical Reviews (LARs) . . . . . . .36 5.4 Summary of Outliers . . . . . . .. . 37
- 6. References..............................................................................................................38 Appendix A - Resumes of Seismic Capability Engineers Appendix B - Screening Verification Data Sheets (SVDS)
Appendix C - Plant Area Summary Sheets (PASS) Appendix D - Limited Analytical Reviews (LARs) Appendix E - Outiler Seismic Verification Sheets (OSVS) Appendix F - Peer Review Correspondence Appendix G - Screening Evaluation Worksheets (SEWS) Note: All but Appendix G are in Volume 1. Appendix G starts in Volume I and continues in Volumes 11
}J through VI.
JAFNPP USl A-46 Seismic Evaluation Report September 1995 page 1/38
n 1. Introduction 1 b 1.1 Purpose The purpose of this report is to document the seismic evaluations performed to address Unresolved Safety issue (USI) A-46 at the James A. FitzPatrick Nuclear Power Plant (JAFNPP), using the Generic implementation Procedure (GlP) by the Seismic Qualification Utility Group (SQUG) [1]. The development of the safe shutdown equipment list (SSEL) and the relay evaluations are documented in a separate report [3]. i
1.2 Background
in early 1987, the NRC issued Generic Letter (GL) 87-02 to owners of operating nuclear plants which were licensed prior to development of modern seismic qualification standards. The recipients of GL 87-02 are referred to as A-46 plants and include JAFNPP. GL 87-02 requires owners to take action to verify the seismic adequacy of important equipment in their plants. The approach embodied in the GIP [1] is explicitly recognized by the NRC as the preferred method for accomplishing this objective. In 1992, the NRC issued Supplement No.1 to GL 87-02 [2] which transmitted Supplemental Safety Evaluation Report No. 2 on SQUG GIP, Revision 2, as corrected on February 14,1992 [1]. References 1 and 2 are the basis for the seismic evaluations described in this report. In Reference 4, NYPA described their approach for resolving USl A-46. This approach was accepted by the NRC in Reference 5. 1.3 Report Organization m The remaining sections of this report are organized as follows: U Section 2," Seismic Design Basis"-The JAFNPP Ground Response Spectra (GRS) and in-Structure Response Spectra (IRS) are described and compared to the Bounding Spectrum from Reference 1. Section 3, " Mechanical and Electrical Equipment Review'- Screening Verification and Walkdown results for mechanical and electrical equipment are discussed. Instances in which the intent of a caveat is met without meeting the specific wording of the caveat rule are identified. A summary of outliers and their resolution is provided. Screening Verification Data Sheets (SVDS) are in Appendix B. Screening Evaluation Worksheets (SEWS) are in Appendix G. Outlier Seismic Verification Sheets (OSVS) are included in Appendix E. Section 4," Tanks and Heat Exchanger Review'- Results of the tanks and heat exchangers review are discussed, including instances in which the intent, but not the letter, of a caveat is met. A summary of outliers and their resolution is provided. The SEWS for tanks are included in Appendix G. There are no outliers for this class of equipment. Section 5," Cable and Conduit Raceway Review"- Results of the raceway review, including bounding samples and outliers, are summarized. The Plant Area Summary Sheets (PASS) are included in Appendix C. The Limited Analytical Reviews (LARs) are in Appendix D. Outlier Seismic Verification Sheets (OSVS) are included in Appendix E. 1.4 PeerReview Dr. John D. Stevenson of Stevenson & Associates performed a peer review of seismic evaluation. The review consisted of selecting 19 representative items of equipment from the seismic SSEL, an independent walk down of those items, and a review of the SRT's evaluation of those items. The correspondence documenting the peer review are included in Appendix F. JAFNPP USl A-46 Seismic Evaluation Report September 1995 page 2/38
- 2. Seismic Design Basis >
+ 2.1 Ground Response Spectrum JAFNPP's horizontal Design Basis Earthquake (DBE) ground response spectrum is shown in Figure 2.1.
. The DBE is a Housner shape with a 0.15g zero period acceleration.
]
The GlP's Bounding Spectrum is also shown in Figure 2.1, One of the fundamental requirements of the , GIP is that a plant's seismic demand (defined by the DBE) be enveloped by the seismic capacity of the ! equipment in the earthquake experience data base (defined by the Bounding Spectrum). Figure 2.1 : demonstrates that JAFNPP meets this requirement. 1.0 ' l : l l: :: l l : ..l, l l l l lll-, l l l ': ll: os ----- t , s a 3- - - - r - - -;- - ; - -; - ; -;- p t
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Figure 2.1 JAFNPP DBE and the GIP's Bounding Spectrum (both curves 5% damped) (The terms Design Basis Earthquake (DBE) and Safe Shutdown Earthquake (SSE) are equivalent. The term DBE is used in this section to be consistent with JAFNPP's UFSAR. The term SSE is used in the remainder of the text to be consistent with the GIP). 2.2 In-structure Response Spectra JAFNPP consists of two building complexes: 1) the reactor building, which houses the reactor pressure vessel, primary shield wall, drywell and the suppression chamber, and 2) the turbine building complex, which includes the turbine building, administration building, radwaste building, screenwell pumphouse and emergency diesel generator building. A dynamic structural analysis was performed as described in Reference 4. The structures were modeled .. as beam elements, The masses of walls, floors, and equipment were lumped discretely at floor elevations and other major structural discontinuities. Since the buildings are founded on bedrock with a shear wave velocity exceeding 5500 ft/sec, any soil-structure interaction effect was considered negligible. In-structure Response Spectra (IRS) were calculated using time history modal superposition. 5% structural damping was used for the turbine building complex (all concrete). The reactor building is a ( combination of concrete and steel construction. Structural damping values ranging between 3% and 5% JAFNPP USl A-46 Seismic Evaluation Report September 1995 page 3/38
were used (the values were based on the strain energy distribution in each mode) The IRS were y calculated using 1% equipment damping and peak spread 15%. For the purposes of A-46, IRS for other equipment damping values were developed by modifying the peaks of the 1% IRS to the appropriate damping value. Reference 4 informed the USNRC that the IRS as described above would be used for the A-46 program. This letter includes a description and plots of the IRS. In their response (Reference 5), the USNRC defined the JAFNPP IRS as " Conservative, Design" per GIP Section 11.4.2. 2.3 Grade Elevation JAFNPP is a level site; the structures are founded on rock and have a shallow soil fill surrounding the buildings. Grade elevation is 272' around all buildings, and 272' is used as the grade elevation for the A-46 project. i O O
- JAFNPP USI A-46 Seismic Evaluation Report September 1995 page 4/38 j
-4L o 3. Mechanical and Electrical Equipment Review t i V i 3.1 Summary of the Review The reviews of the seismic adequacy of mechanical and electrical equipment on the JAFNPP Seismic Safe Shutdown Equipment List (SSEL) were performed in accordance with Section l1.4 of the Generic implementation Procedure (GIP) [ Reference 1]. j Each piece of equipment was reviewed by a Seismic Review Team (SRT) consisting of two or three Seismic Capability Engineers (SCEs), and always included at least one licensed professional engineer.
Plant craft personnel provided assistance in opening equipment for intemalinspections and performing bolt tightness checks. Resumes and SQUG certifications for the SCEs are provided in Appendix A. l The walk downs were performed in three clusters: April 1994 (A&C train on-line walk downs), September l 1994 (B&D train on-line walk downs), and December 1994/ January 1995 (outage walk downs). i Signed Screening Verification Data Sheets (SVDS) for all seismic SSEL equipment item are contained in Appendix B. Screening Evaluation Worksheets (SEWS) are contained in Appendix G. The SEWS document the details of the evaluations including caveats, comments by the SRT, anchorage evaluations, photographs, sketches, and bolt tightness check documentation (due to their bulk, the SEWS are not included in the submittal to the NRC, but are available upon request). 3.1.1 Seismic Capacity vs. Demand For equipment on the seismic SSEL, Seismic Capacity vs. Demand was evaluated using one of the l following: l
- 1. Bounding Spectrum vs. Safe Shutdown Earthquake (BS vs SSE, GlP ll.4.2 Method A.1) l
- 2. 1.5x Bounding Spectrum vs. Conservative Floor (In-Structure) Response Spectrum (1.5BS vs FRS, GIP ll.4.2 Method B.1),
(Note that Generic Equipment Response Spectra (GERS) were not used.) When the first option (BS vs SSE) was used, three requirements had to be satisfied:
- 1. The BS has to envelope the SSE. This is demonstrated in Figure 2.1.
- 2. The equipment has to be within about 40' of grade. As noted earlier, Elevation 272' v:As used as the grade elevation for the A-46 project.
The base of the turbine building complex varies, but is typically founded on excavated rock at about elevation 245', with structural backfill up to the top of the rock excavation at about 265', and common backfill up to yard grade at 272'. Almost all the equipment in the turbine building complex on the seismic SSEL is at elevation 300' or lower (there are a few items of control room HVAC equipment that are at about elevation 310'). Based on this, all equipment in the turbine building complex on the seismic SSEL was considered to meet the "within about 40' of grade" requirement. The reactor building is founded at elevation 222', with a sand backfill in the annular space between the exterior wall and the excavated rock up to elevation 265', and then common backfill up to the yard grade at elevation 272'. The seismic SSEL equipment in the reactor building is in the crescent areas (below 272') and on floor elevations 272',300',326', and 344'. All of the seismic SSEL equipment inside the drywellis below elevation 300'. Equipment on or below elevation 300' was considered to meet the "within about 40' of grade" requirement; the equipment on elevations 326 and 344 was not. JAFNPP USl A-46 Seismic Evaluation Report September 1995 page 5/38
1 I l
- 3. The equipment has to have a fundamental frequency of 8 Hz or greater. This was determined by the
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t b Seismic Review Teams on an equipment-by-equipment basis. The bases for these judgements were 1 Table C.1-1 of the GIP [1], the EPRI guidelines [12), and the experience of the Sesimic Review Team. Equipment judged to be less than 8 Hz included motor control centers, vertical pumps, and equipment
; supported on vibration isolators.
If an item of equipment failed to meet either the "within about 40' of grade" requirement or the 8 Hz requirement, then 1.5x BS vs. FRS was used. In this case there is no elevation or frequency requirement; the only requirement is that the horizontal floor response spectra (NS and EW) are enveloped by 1.5x the Bounding Spectrum. Figure 3.1 shows 1.5x Bounding Spectrum vs the envelope of the turbine building horizontal floor response spectra at elevations 272 and 300. Except for a negligible exceedance at 33 Hz, the turbine building spectra are enveloped. 1.5
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Turtxne Building l l l ,l:l l l l l llll 1 10 100 Frequency (Hz) Figure 3.1 1.5x Bounding Spectrum vs. the Envelope of the Turbine Building Floor Response Spectra (both curves 5% damped) Figure 3.2 compares the reactor building floor response spectra to 1.5x the Bounding Spectrum., The only exceedance is the elevation 272' spectrum at about 15 Hz (The peak of the elevation 344' spectrum exceeds 1.5x BS by about 1%, however, this is considered acceptable per the discussion in GIP l1.4.2 under the paragraph entitled " Enveloping of Seismic Demand Spectrum"). , JAFNPP USl A-46 Seismic Evaluation Report September 1995 page 6/38
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0 1 10 100 Frequency (Hz) Figure 3.2 1.5x Bounding Spectrum vs. the Reactor Building Floor Response Spectra (all curves 5% damped) , l Based on the above, the only equipment that does meet the Seismic Capacity v Demand requirement l would be equipment with a fundamental frequency less than 8 Hz that is located in the reactor building on I
. elevation 272' or below. The only equipment that fell into this category were the motor control centers (MCCs) on elevation 242' and 272'. These MCCs are also outliers because they are less than 18" deep.
- They are discussed in more detailin Section 3.3, Summary of Outliers. 1
~ The Seismic Capacity vs. Demand basis used for each item of equipment on the seismic SSEL is listed in -
the Screening Verification Data Sheets (SVDS) in Appendix B. Note that the fact that an item of equipment met both the 8 Hz requirement and the "within about 40' of grade" requirement, does not necessarily mean that BS vs. SSE was used as the basis. Per the GIP, either BS vs. SSE or 1.5x BS vs FRS could have been used in that situation. Of course, if one or both of the requirements were not met, then only 1.5x BS vs. FRS was used as the basis. .! l 3.1.2 Equipment Class Description There are a total of 443 items of mechanical and electrical equipment on the seismic SSEL (note that this
- does not include equipment identified as " rule-of-the-box"- those equipment items are identified on the composite SSEL in Reference 3). The following list, organized by equipment class, provides a brief description of the equipment on the seismic SSEL. The description includes the number of items in the ;
equipment class, the location of the equipment, and the manufacturer. ; The Screening Verification Data Sheets (SVDS ) in Appendix B lists each item of equipment and summarizes the results of the evaluation. More detailed information for each item of equipment (including screening results, field notes, detailed anchorage evaluations, and photographs) is provided in the Screening Evaluation Worksheets (SEWS) in Appendix G. Those equipment items that did not meet the GIP screening criteria were identified as outliers and are discussed in Section 3.3. O V JAFNPP USl A-46 Seismic Evaluation Report September 1995 page 7/38
j (% 1. Motor Control Centers There are 23 MCCs on the seismic SSEL. Eight (8) are in the turbine building complex (4 in the electrical bay on 272' , 2 in the diesel generator area on 272', and 2 in the control room HVAC area on 300'), and 15 are in the reactor building (8 on elevation 242', 5 on elevation 272' and 2 on elevation 344'). Twenty (20) of the MCCs are 13' deep GE Model 7700s,1 is a 20* deep GE Model 7700, and the two on elevation 344' of the reactor building are new GE Model 8000s.
- 2. Low Voltage Switchgear There are 4 low voltage switchgear on the seismic SSEL. Two (2) are in the turbine building complex l (electrical bay on 272') and 2 are in the reactor building on 300'. All 4 are GE Type AKD-5. Each switchgear is part of a load center consisting of the switchgear, a dry-type transformer, and a load-interrupter (disconnect) switch.
- 3. Medium Voltage Switchgear l There are 6 medium voltage switchgear on the seismic SSEL: ;
four (4) GE Breakmaster load-interrupter switches in the load centers described above under Low Voltage Switchgear, and ) two (2) in the diesel generator area (turbine building 272'); each is a bank of ten (10) 1200 Amp GE Magne - Blast Type AMH 476-250 4KV breakers. ; 1 / 4. Transformers There are 11 transformers on the seismic SSEL.: seven (7) small (7.5KVA or 15KVA), wall-mounted transformers manufactured by Acme Electric and located in several areas on elevation 272' of the turbine building complex, and four (4) 1000 KVA dry-type substation transformers in the load centers described above under Low l Voltage Switchgear. Of these four, three are manufactured by GE and one is a new installation manufactured by ABB.
- 5. Horizontal Pumps 1 l
There are 13 horizontal pumps on the seismic SSEL: eight (8) 1/2 HP diesel generator fuel oil transfer pumps (Roper pump / Westinghouse motor) on elevation 272' of the turbine building complex, two (2) 50 HP pumps (Union pump / GE motor) that are part of the Standby Liquid Control system on elevation 326' of the reactor building, the 3200 HP, Byron-Jackson / Terry Turbine, turbine driven HPCI pump on elevation 227' of the reactor building (this includes the main pump, booster pump, and the turbine), and the 7.5 HP, Tuthill Pump Co., HPCI turbine tube oil pump. A U JAFNPP USI A-46 Seismic Evaluation Report September 1995 page 8/38 1
1
- 6. Vertical Pumps There are 10 vertical pumps on the seismic SSEL: I four (4) RHR pumps; all four are Byron-Jackson 1000 HP centrifugal pumps and are on elevation 227' of the reactor building, and I four (4) RHR service water pumps, and two (2) emergency service water pumps; all six are Allis Chalmers 350 HP deep-well pumps and are located in the service water pump area on elevation 255' of the turbine building complex.
- 7. Fluid-Operated Valves There are 94 fluid-operated valves on the seismic SSEL, located throughout the plant. Manufactures include Crosby Valve, Masonellian, Fisher Rockwell, Atwood & Morrill, and others.
- 8. Motor-Operated and Solenoid-Operated Valves There are 39 MOVs and 12 SOVs on the seismic SSEL located throughout the plant (note that this does not include those SOVs that were treated as " rule-of-the-box" with the associated AOV). MOV manufacturers include Anchor / Darling, Powell, and Velan; all with Limitorque operators. The 12 SOVs are all manufactured by the Automatic Switch Company (ASCO).
- 9. Fans
- 1 I
There are 16 fans on the seismic SSEL: b
\ four (4) 7.5 HP,14500 CFM, axial fans manufactured by Joy and located in the control room HVAC ,
area on elevation 300' of the turbine building complex (2 exhaust the control room and 2 exhaust the I relay room), and four (4) 1 HP,1000 CFM centrifugal fans manufactured by Buffalo Forge, used to exhaust the battery rooms, and located on top of the battery rooms on elevation 272' of the turbine building complex, and . two (2) 5.0 HP axial fans manufactured by Joy, used for battery room recirculation, and located on top of the battery rooms on elevation 272' of the turbine building complex, and four (4) 30,000 CFM axial fans manufactured by Joy, used for diesel generator ventilation, and located in the diesel generator area on elevation 272' of the turbine t;uilding complex, and two (2) 2.0 HP,13,000 CFM duct-mounted axial fans manufactured by Greenheck Fan, used to exhaust the service water pump area on elevation 255' of the turbine building complex. O , JAFNPP USI A-46 Seismic Evaluation Report September 1995 page 9/38
- 10. Air Handlers There are 20 air handlers in the seismic SSEL:
four (4) 13,150 CFM,20 HP Trane AHUs located in the control room HVAC area on elevation 300' of the turbine building complex (2 ventilate the control room and 2 ventilate the relay room), and two (2) 5,700 CFM,2 HP Trane AHUs used to ventilate the chiller room, and located in the chiller , room (adjacent to the control room HVAC area) on elevation 300' of the turbine building complex, and two (2) Trane AHUs used to ventilate the battery rooms, and located on top of the battery rooms on elevation 272' of the turbine building complex, and ! I two (2) 16,500 CFM Buffalo Forge AHUs used to ventilate the electrical bays, located in the HVAC area above the electrical bays on elevation 286' of the turbine building complex, and j ten (10) 10,800 CFM, SHP Buffalo Forge AHUs used to ventilate the crescent areas of the reactor building. They are located throughout the crescent areas, typically at an elevation of about 242'. Class 10 also includes approximately 60 dampers - both motor operated dampers that are typically mounted in-line with the ducts near the AHUs and fans, and fusible-link fire dampers that are typically , i mounted in an opening in a reinforced concrete or concrete block wc!!
- 11. Chillers There are two Trane chillers on the seismic SSEL. Both provide chilled water from control room ventilation p and are located in the chiller room (next to the control room HVAC area) on elevation 300' in the turbine V building complex.
12.' Air Compressors There are no air compressors on the seismic SSEL.
- 13. Motor-Generators There is one motor-generator set on the seismic SSEL. It is located in the electrical bay on elevation 272' of the turbine building complex.
- 14. Distribution Panels !
There are 15 distribution panels on the seismic SSEL. All are manufactured by GE and all are in the turbine building complex; 13 are wall mounted circuit breaker panels in the relay room (elevation 284') and i diesel generator area (elevation 272'), and 2 are floor mounted switchboards in the station battery area j (elevation 272'). O JAFNPP USl A-46 Seismic Evaluation Report September 1995 page 10/38 b
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- 15. Batteries on Racks i
V There are 4 sets of battery racks on the seismic SSEL: two (2) sets house the station batteries (Gould NCX-2400 lead calcium cells) and are located in the battery cubicles on elevation 272' of the turbine building complex, and two (2) sets house the LPCI inverter batteries (Excide EC-19 lead calcium cells) and are located on elevation 344' of the reactor building.
- 16. Battery Chargers and Inverters There are 4 sets of battery chargers / inverters on the seismic SSEL:
two (2) support the station batteries, are manufactured by Power Conversion Products, and are located in the battery cubicles on elevation 272' of the turbine building complex, and two (2) support the LPCI inverter batteries, are manufactured by Exide, and are located on elevation
- 344' of the reactor building.
- 17. Engine-Generators There are four (4) 2400 kilowatt Bruce GM emergency diesel generators on the seismic SSEL. All are located in the diesel generator area on elevation 272' of the turbine building complex.
- 18. Instruments on Racks hL/ There are 25 items classified as instruments on racks on the seismic SSEL. These include both welded steel racks containing multiple instruments, and individually mounted instruments that are typically anchored to a reinforced concrete wall. They are made by a number of different manufacturers. All of the instruments are on various elevations in the reactor building except for one level transmitter that is located in the pit at the base of the condensate storage tanks.
- 19. Temperature Sensors There are 36 temperature sensors on the seismic SSEL:
four (4) are Bums Engineering temperature sensors attached to the ceiling of the diesel generator rooms on elevation 272' of the turbine building complex, and thirty-two (32) are Conax Corporation temperature monitors mounted to the bottom of the torus on elevation 227 of the reactor building.
- 20. Instrumentation and Control Panels and Cabinets There are thirty-five (35) control panels and cabinets on the seismic SSEL. All are in the turbine building complex: 18 in the diesel generator area (elevation 272'),12 in the relay room (elevation 284'),4 in the control room (elevation 300'), and 1 in the electrical bay. The 4 control room cabinets and 8 of the cabinets in the relay room were manufactured by GE, the rest were manufactured by a number of different vendors.
O JAFNPP USl A-46 Seismic Evaluation Report September 1995 page 11/38
p 3.1.3 Equipment Anchorage ('j The different types of equipment anchorage used at JAFNPP are discussed below. The discussion is organized by anchorage type and describes the type of equipment anchored in that manner and how it was evaluated. Detailed information on equipment anchorages, including field sketches, calculations, and bolt tightness check evaluations are included with the Screening Evaluation Worksheets (SEWS) in Appendix G. Those items of equipment that did not meet GlP anchorage requirements were identified as
- outliers and are discussed in Section 3.3.
Per the plant reinforced concrete drawings, the concrete at JAFNPP was specified to have a compressive , strength of 3000 psi at 28 days. Anchor bolt reduction factors were applied as required Per GlP Appendix B. Cast-in-Place Bolts All horizontal and vertical pumps and the diesel generators are anchored with cast-in-place bolts. Anchorage details and equipment weights were obtained from plant drawings, and detailed anchorage calculations were performed per the requirements of GIP 11.4.4 and Appendix B. Welding to Sills Most of the floor-mounted electrical equipment - motor control centers, switchgear, transformers, and cabinets - are welded to sills: steel channels embedded in a reinforced concrete floor slab. A typical sill detail is shown in Figure 3.3. When the floor slab was poured, a spacer was used to form a trench. The spacer was then removed, the steel was placed and anchored, and the trench was filled with grout.
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k X w--p 61LGSTRAP l 2*-0 p0.C. DE T. 'A' hO SCAT.E Figure 3.3 Typical embedded steel detail (from JAFNPP Dwg FE-38AA Rev 10). For deep equipment - switchgear, tranformers, and control room benchboards - the shear capacity govems the anchorage evaluation. The sill has a high shear capacity, so,in shear, an equipment's anchorage capacity is govemed by the weld connecting the cabinet to the sill. In the case of narrow equipment - motor control centers and vertical cabinets - the capacity of the anchorage is govemed by the uplift capacity. The uplift capacity of this detail depends on the relative capacity of the weld between the cabinet and the sill and the anchorage of the sill to the floor slab. The uplift capacity of the sill was based on the uplift capacity of the 1/2" expansion anchors - no credit was taken for the grout. In addition, only one of each pair of expansion anchors was considered: typically, the A weld between the cabinet and the sill is close to the edge of the sill, so the uplift load would tend to flow JAFNPP USI A-46 Seismic Evaluation Report September 1995 page 12/38
. _ _ . _ _ _ ._ - _ _ . - - _ ._ _ ~_ _ . . _ _ _ . _ _ _ _ _ _ _ _ - - _ - _ - _ _ _ - . t to the expansion anchor on that side. In most cases, the capacity based on one expansion anchor is less
.V[s} than the capacity of the weld between the cabinet and the sill and therefore govemed the anchorage
. evaluation.
Note that GIP 11.4.2 and ll.C.2 specify that either an expansion anchor's embedment and tightness be checked, or the Reduced Inspection Altemative (GIP.l!.C.2.10) be applied (this attemative essentially requires that an additional reduction factor of 0.5 be applied). Obviously, the embedment and bolt tightness checks could not be performed. In addition, per GlP.ll.C.2.10, the Reduced Inspection Attemative could not be applied because a reduction had to be taken for concrete strength and, in some cases, an additional reduction for essential relays. The Seismic Review Team decided to calculate the uplift capacity of the siil based on the nominal capacity of one 1/2" expansion anchor every 24" , a 0.75 reduction factor for concrete strength, and an additional 0.75 reduction factor for equipment containing essential relays; no additional reduction was applied This results in an uplift capacity of 860 lb/ft of sillin the case of no essential relays, and 640 lb/ft with essential relays. In the judgment of the Seismic Review Team, this is a reasonable capacity, and the lack of the embedment and tightness checks is adequately compensated for by ignoring the second expansion anchor and ignoring any capacity provided by the grout. Welding / Bolting to Building Steel Equipment welded or bolted to building steel includes the motor control centers, instrument racks, and air handling units on or near the elevation 242' platform in the reactor building crescents, the air handling , equipment hung from the ceilings in the diesel generator areas and chiller room, and some of the , distribution panels in the relay rooms. Evaluations were performed per the requirements of the GIP; in some cases where the welding was obviously adequate, it was so stated by the Seismic Review Team on the SEWS and no explicit calculations were performed. H( Concrete Expansion Anchors Equipment anchored with concrete expansion anchors includes most of the floor-mounted HVAC
. equipment in the station battery area, control room HVAC area and electrical bay, the station battery racks, the LPCI battery racks and battery charger / inverters, a number of small electrical cabinets in the i diesel generator area, the diesel generator air start receiver tanks, and a number of items of small wall-mounted equipment such as circuit breaker panels and single instruments.
A total of 79 items of equipment on the seismic SSEL received bolt tightness checks. Documentation is included with the SEWS in Appendix G. A few items of equipment that are of recent vintage were installed under plant procedures that required a documented bolt tightness check. This equipment was not checked again, the documentation was reviewed and referenced in the SEWS. Small wall mounted 1 equipment was tug-tested by the Seismic Review Team. Anchorage evaluations were performed per the requirements of GIP 11.4.2 and GIP Appendix C. The evaluations are attached to the SEWS in Appendix G of this report. 3.1.4 Seismic Interaction The equipment screening evaluations included evaluation for potential seismic interaction concerns, per GIP Section 11.4.5 and Appendix D. Those items of equipment that did not meet GlP interaction requirements were identified as outliers and are discussed in Section 3.3. Prior to performing the walk downs, block walls were identified as a possible interaction concem. The JAFNPP 80-11 block wall submittal (References 7 and 8) was reviewed. The submittal contains a set of drawings locating the block walls seismically analyzed and qualified in the 80-11 program. During the l walk downs, when a block wall was identified as a potential interaction hazard, these drawings were ] JAFNPP USl A-46 Seismic Evaluation Report ; September 1995 page 13/38
checked. If the wall was included in the 80-11 effort, it was judged not to be an interaction hazard and p) ( V noted in the SEWS. Three block walls were encountered that were not part of the 80-11 effort: the walls around the two SCRAM Discharge Tank cubicles on elevation 272' of the reactor building, and a small fire protection barrier next to a motor control center also on elevation 272' of the reactor building. The tank cubicles' walls were installed after the 80-11 effort and were seismically designed - a reference is included in the SEWS for the tanks. The fire protection barrier was evaluated by the Seismic Review Team and found acceptable - the evaluation is attached to the SEWS for 71MCC-161. 3.2 Instances ofIntent but not Letter of Caveat Met Instances in which the intent of a caveat is met without meeting the specific wording of the caveat rule are listed in Table 3.1. O l 1 O O , JAFNPP USI A-46 Seismic Evaluation Report September 1995 page 14/38
/ (R s Tcble 3.1 Equipment Classes 0 - 20, instances of Intent but not Letter of Caveat Met Cl ID Description Caveat and Comments 1 71MCC-253 600V Motor Control Anchorage Caveat 10. The adequacy of embedded steel, grout pads or large concrete pads have been 71MCC-263 Center (Bus 125300 evaluated.
and 126300) These MCCs are welded to embedded sills. The sills are as described in Section 3.1.3, except that the drawing (JAFNPP Dwg No. FE-38AG Rev 8) does not indicate any concrete expansion anchors. An asterisk was applied because, without the expansion anchors, the sill is anchored in a grout pocket rather than directly in structural concrete. i A capacity was calculated by treating the sill as anchored by a cast-in-place bolt in the area around the strap welded to the bottom of the channel. This resulted in a pullout capacity for the sill of about 2 kips /ft. Using this capacity, the anchorage has a factor of safety of about 6. Given the large margin, the Seismic Review Team > judged the anchorage acceptable. t 4 71PT-71ACUPS Uninterruptable Bus TRN/BS Caveat 1 - Earthquake Experience Equipment Class
^ ""
The GIP's equipment class description states * .. Distribution transformers typically have primary voltages of 480 MC 25 volts stepping down to secondary voltages of 120 to 240 volts.. *. This transformer has a primary valtage of 600 . volts. The transformer's weight (300 lbs) and dimensions (17"W x 22"H x 22*D) are within the class description ! range, so it was judged to fall within the experience data base. ; Anchorage Caveat 6 - For bolted anchorages, any gaps under the base are less than 1/4*. The transformer is anchored with four (4) 1/2* anchors to a wall. There is a 7/8" gap between the back of the i transformer and the wall due to a hex-shaped spacer which is threaded on each bolt (probably to allow air circulation around the transformer). The calculated anchor loads are low (335 lb tension /137 lb shear), so this configuration was judged acceptable. l 7 27PCV-134A CAD Train A & B Valve FOV/BS Caveat 4 - Mounted on 1 Inch Diameter Pipe Line or Greater. ; 27PCV-134B Operating Nitrogen FOV/BS Caveat 5 - Valve Operator Cantilever Length Pressure ControlValves The valve is mounted on a 1/2" line, but as the valve is quite small (the measured offset is only 5"), it was judged that the valve meets the intent of these caveats. i i JAFNPP USl A-46 Seismic Evaluation Report September 1995 page 15/38
s i i i ! Cl ID Description Caveat and Comments 7 27RV-101A Liquid Nitrogen Tank A FOV/BS Caveat 4 - Mounted on 1 inch Diameter Pipe Line or Greater. i 27RV-1018 and Tank B Relief FOV/BS Caveat 5 - Valve Operator Cantilever Length anes The valve has an offset of 27" from the line to the top of the operator and is mounted on a line that is < 1" in < diameter. 'rk,ecer, the valve is anchored by a welded steel bracket that is clamped to the base of the stem. 4 The line is too small to generate significant loads on the valve, therefore this configuration was judged as .j meeting the intent of the caveats. 7 29AOV-80A - D Inboard and Outboard FOV/BS Caveat 1 - Earthquake Expenence Equipment Class. _ 29AOV-86A - D Mam Steam lh These are large piston-operated AOVs on a 24" line with a 130" offset. ' The valve is somewhat larger than the - piston-driven AOVs in the expenence data base (Per GlP Figure B.7-2 the maximum offset is 100"), but based
- on its well engineered construction it was judged at least robust as the AOVs in the data base.
1 7 70PCV-100A1 Control Room and FOV/BS Caveat 2 - Valve Body Not of Cast iron
- 70PCV-100A2 Relay Room Chh These are small pressure control valves (6" offsets) on well supported 2.5" lines. The valve bodies are cast iron.
7 00 but as the offset is small and the lines are well supported, significant stresses will not be developed Therefore the mtent of the caveat is met. 7 70TCV-123A Control Room and FOV/BS Caveat 1 - Earthquake Experience Equipment Class 70TCV-1238 Room AHU 9A These valves are mounted on a 3/4" line, have an offset of 41", weigh 140 lbs, and have an electro-hydraulic si,eia r. Electro-hydraulic opei iors are not in the expenence data base, but given the valves good Tem NM construebon and relatively light weight, the Seismic Review Team judged its seismic capacity to be at least as y high as the AOVs in the experience data base. Note that while the valves' seismic capacity was judged acceptable, the valves were declared outhers because they have a 41" offset and are mounted on a 3/4" line. l They are included in the outleer discussion in Sechon 3.3. 8 10MOV-34A RHR Torus Cooling MOV/BS Caveat 5 - Valve Operator Cantilever Length for Motor-Operated Valves. i- 10MOV-348 Supply Valves These valves are on 14" lines, have an offset of 55*, and an operator weight of 960 lbs.I The GIP Figure B.8-5 limits for a 14" line are 100" and 750#. The operator weight exceeds the limit but the valve was judged as -; meetmg the intent of the caveat because the actual weight-offset product (55 x 960 = 52800) is less than the 4 required weight-offset product (100 x 750 = 75000) and the actual weight and offset are no more than 130% of the required values. Note that this approach is identical to that specified in the GlP under FOV/BS Caveat 6 JAFNPP USI A-46 Seismic Evaluabon Report September 1995 page 16/38 i 4 1
O O O Cl ID Description Caveat and Comments 17 93EDG-A Emergency Diesel Anchorage Caveat 5 - Factors Affecting Anchorage Capacity 93EDG-B Generators Each diesel generator is anchored with sixteen (16) 1.25" J bolts. Each bolt is embedded 15" into the floor slab. 93EDG-C GIP Appendix C.4.2 states that a J-bolt with an embedment less than 16D (20" in this case) is an outlier. 93EDG-D However, that section also states that embedment affects only the pullout capacity of the bolt, and not the shear capacity. As the diesel generator has a wide foot print (approx. 6' wide x 30' long), a low center of gravity (4' above the floor per manufacturer's drawing), and a low seismic load (0.28g using the 1.25 x 1.5 the ZPA of the SSE), the anchorage is adequate by a factor of about 2 even if the bolts have no pullout capacity. The anchorage was evaluated assuming 7/8* diameter J-bolts (the maximum diameter that meets the 16D embedment requirement) - these yielded a margin of nearly 4. Based on this, the Seismic Review Team judged that the intent of the caveat is met. 20 27 MAP Monitoring Analysis Anchorage Caveat 4 - The adequacy of the anchorage installation has been evaluated Panel The welds connecting the panel to the embedded steel could not be inspected by the Seismic Review Team (SRT) because it would require removing floor tiles. The welds had been inspected previously as part of an effort at JAFNPP to verify the anchorage of electrical equipment (see JAF-CALC-MISC-00285). The SRT judged that this inspection met the intent of the caveat. JAFNPP USl A-46 Seismic Evaluation Report September 1995 page 17/38
3.3 Summary of Outilers A total of 62 items of mechanical and electrical equipment were named outliers A description of each equipment outlier and its resolution is provided in Table 3.2. The corresponding Outlier Seismic Verification Sheets (OSVS) are included in Appendix E. J i l O i . O JAFNPP USl A-46 Seismic Evaluation Report September 1995 page 18/38
O O V U V Ts.ble 3.2 Equipment Classes 0 - 20, Outliers Cl ID Description Outlier Issue and Resolution 0, 7 03TK-125 One set of Outlier issue: 03TK-128 accumulators and
- a. Equipment Class 0- These items are all mounted on a tube steel rack. The tube steel rack is part of a 03AOV-126 valves on the Hydraul.ic bolted group of 14 identical racks (7 pairs back to back). Each rack is bolted to an embedded steel frame with 03AOV-127 Control Rod Drive four U2 A307 structural bolts. The embedded steel frame is anchored with 3/4" CIP bolts with a 15.5" (H ) rach embedment.
- b. Seismic Interaction: There is an unanchored distribution panel rack on the east side of the east HCU rack.
The rack is wide enough not to tip over, and probably far enough away not to slide into the HCU rack, but given the critical nature of the HCUs, the SRTjudged this an interaction outlier and recommended that it be restrained..
- c. Seismic Interaction: The HCU charging bottles on the north side of the east HCU rack are loosely chained to a building column. The SRT judged them an interaction concem and recommended that they be more securely fastened.
Resolution:
- a. The rack does not fit into any of the 20 classes, however the SRT judged the capacity adequate due to its substantial construction and the margin between the SSE and the Bounding Spectrum. Note that the valves meet the Class 7 caveats and that the rack's anchorage was evaluated and found adequate.
- b. The rack was secured by chains to nearby er.isting structures.
- c. The charging bottles were removed.
0 11 EV-14A SLC Double Squib Outlier issue: 11EV-14B A at Equipment Class 0- Explosive valves do not fit any of the equipment classes. e Va es Resolution: These are small, compact devices on well supported 1.5" lines. Due to their small size and that they are mounted on a well supported line, the SRT judged them not vulnerable to damage by a seismic event. 1 71 BMCC-1* Various Motor Control Outlier issue: enters (MCCs) Equipment Class
Description:
All of these MCCs (except 71BMCC-6) are 13* deep GE Model 7700 and are anchored _only to the floor. Per GIP Appendix B.1.1, to be included in the equipment class, MCCs less than JAFNPP USI A-46 Seismic Evaluation Report September 1995 page 19/38
O O O l Cl ID Description Outlier issue and Resolution 71BMCC-4* about 18' deep should be top braced or attached to a wall (71BMCC-6 is a 20' deep GE Model 7700, so it 71BMCC-6* satisfies the equipment class description). l Capacity vs. Demand: The SRT judged the MCCs to have a fundamental frequency less than 8 Hz, therefore e pady n Demand is based on 1.5x Bound SWmm n Roomesponse Spe&a @S). De MS for 71MCC-153* elev tion 272' of the reactor building exceeds 1.5x Bounding Spectrum near 15 Hz by about 20%. This FRS is 71MCC-155* the demand for the MCCs located on elevation 272' of the reactor building and in the reactor building crescents 71MCC 161* (those MCCs are denoted with an asterisk). 71MCC-162* i 71MCC-163* Resolution: 6 Both the Equipment Class Description and the Capacity vs. Demand issues are resolved by the following. 71MCC-252 Reference 9 documents a shake table test of a 13" deep GE7700 MCC. The test consisted of a series of 40 71MCC-253 see to 60 sec long single frequency sine dwell tests of various directions, frequencies and amplitudes. The 71MCC-254 conclusion of the test report was that the MCC can withstand a 0.5g input over the seismic frequency range 71MCC-261 (from approx. 2 to 34 Hz) in all three axes. If the base is reinforced, the input level can be increased to 1.0 g. 71MCC-262 The MCCs at JAF do not have tne base reinforcement described in Reference 9, so only the 0.5g input value CC can be used. A 0.5g sine dwell test corresponds to a 5% damped test response spectrum with a 0.5g ZPA and a 5.0g peak. As a series of sine dwell tests at varying frequencies were conducted, the test response spectra is represented in Figure 3.4 as a straight line at 5.0g from 3 Hz to 33 Hz (the peak) and another straight line at 0.5g above 33 Hz (the ZPA). , i l JAFNPP USI A-46 Seismic Evaluation Report September 1995 page 20/38
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%J Cl ID Description Outlier issue and Resolution
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a -=ee Figure 3.4 Comparison of Outlier MCCs' FRS to Test Response Spectrum (both curves 5% damped) Also shown in Figure 3.4 is the envelope of all the horizontal FRS at which outlier MCCs are located (this is the .i envelope of the turt>ine building complex 272' and 300', and reactor building 272'). The figure shows that the seismic capacity envelopes the seismic demand except for a negligible amount between 33 Hz and 40 Hz. - The SRT judged the above adequate demonstration that the seismic capacity of the MCCs exceeds the ! demand. 1 71BMCC-6 Reactor Building DC Outlier issue: Motor Control Center Seismic Interaction (Essential Relays): The MCC contains essential relays and abuts (but is not attached to) a 4" conduit. The MCC could impact the abutting equipment, resulting in relay chatter. 7 t Resolution: Work Request WR-95-02626-00 was issued to shift the conduit to provide adequate clearance. l Work was completed on 6/21/95. JAFNPP USl A-46 Seismic Evaluation Report : September 1995 , page 21/38
- O O O Cl ID Description Outlier issue and Resolution 1 71MCC-153 600V MCC (Bus Outlier issue:
1153 % ) Bounding Spectrum Caveats (Other Concems): The leftmost (first) bay of 71MCC-153 is missing the back left self-tapping screw that secures the MCC to its base channel. Seismic Interaction (EssentialRelays): There is an unsecured ladder stored behind 71MCC-153. This is an interaction concem because the MCC contains essential relays. Resolution: Corrective maintenance completed on 5/8/95 per Work Request 95-00606-00 (for screw). 1 71MCC-161 600V MCC (Bus Outlier issue: IIOI ) Bounding Spectrum Caveats (Other Concems): The leftmost (first) bay of 71MCC-153 is missing the front left self-tapping screw that secures the MCC to its base channel. Seismic Interaction (Essential Reuys): There is an abutting rod hung raceway hanger that will impact the MCC. This is an interachen ccricem because the MCC contains essential relays. Resolution: Corrective raaintenance completed on 6/27/95 per Work Request 95-03779-00 (for screw). 2 71L25 600V Switchgear (Bus Outlier issue: 25%) Anchorage: At the time of the waltdown, it was noted that switchgear was attached to the embedded steel with only two plug welds (both in the rear). The SRT judged that this would not meet GIP requirements, and as the switchgear would be de-energized for only a short period of time, it was decided to add the welds shown in the sketch WR-95-00204-00 SK-001. The welding was completed and walked-down by the SRT that same day. Resolution: The anchorage was upgraded underWork Request WR-95-00204-00 and Design Change D1 055. 7 70TCV-123A Control Room and Outlier issue: 70TCV-123B Relay Room AHU-19A Bounding Spectmm Caveats: The valve is mounted on a 3/4* line, FOV/BS Caveat 4 requires that the line diameter be l' or greater. The valve has an offset of 41". Te e Co I Valves Resolution: The valve and pipe were as-built and analyzed (JAF-CALC-SWS-02105). Pipe stresses were shown to be within code allowables. JAFNPP USI A-46 Seismic Evaluation Report ' September 1995 page 22/38
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h ,O O b) c v Cl ID Description l Outlier issue and Resolution 7 10SOV-68B RHR B Testable Check Outlier issue: Air Supply isolation Bounding Spectrum Caveats: 10SOV-68B is dangling from its tubing and electric connections. The SOV is olenod Valve very lightweight and the connecting lines are flexible. so, in the SRT's judgment, it would not be damaged in a seismic event, but it would be good engineering practice to secure this SOV Resolution: PID 61612 was written to identify the condition (WR 95-00098-00). A modification is planned for the 1996 maintenance outage (D1-95-111). 9 72FN-46A Battery Room Exhaust Outlier issue: ans Bounding Spectrum Caveats: The fans are each suppor1ed on four vibration isolators which are expansion l anchored to an r/c slab. The isolators are designed to resist uplift and lateralloads, and the evaluation attached to the SEWS shows that the isolators and their anchorage are adequate. However, the isolators are missing the locknut between the head of the isolator's adjustment bolt and the equipment skid. This locknut is i required to prevent uplift. The anchorage evaluation attached to the SEWS shows that there is a possibility of a net uplift on the isolators. Resolution: Design Change D1-95-080 issued to replace isolator locknuts and repair the anchorage. 10 67E-11 East and West Vent Outlierissue: 67E-14 e Tunnel Cooling Anchorage: The cooling coil is intemal to a large air handling unit (104* wide x 94" high x 180" long), which, in - addition to the coil, contains several filters (the fans and motors are extemal). Only two sides of the AHU are I accessible. The capacity of the visible anchorage is less than the demand. No drawings couid be !ocated that document the AHU's anchorage. Resolution: Either determine if there are any more anchors on the inaccessibie side and re-evaluate, or upgrade the accessible anchorage (WR 95-06353-00,06354-00). 10 67UC-16A East and West Outlier issue: 67UC-16B Electrical Bays' Unit Anchorage: The anchorage was judged inadequate because: 1) the anchorage configuration puts significant Coolers bending stresses on the anchor bolts,2) some of the nuts are missing or improperly seated,3)the flange of the AHU housing is bent at some anchors,4)some anchors show signs of corrosion. Resolution: Work Requests 95-02524-01 and 95-02511-01 were issued to repair the anchorage.. JAFNPP USI A-46 Seismic Evaluation Report September 1995 page 23/38 1
O O V d d Cl ID Description Outlier issue and Resolution 10 70AHU-12A Relay Room AHUs Outlier issue: 70AHU-128 Anchorage: These four fan units all have the same anchorage: each is supported on 4 vibration isolators that
^ " ' " ^" 8 are expansion anchored into an r/c floor stab. The isolators are designed to resist uplift and lateralloads, and 3 the evaluation attached to the SEWS shows that, if property installed, the isolators and their anchorage are adequate. The fans are outliers because:
- 1. The isolators are missing the locknut between the head of each isolator's adjustment bolt and the equipment skid. This locknut is required to prevent uplift (the anchorage evaluation showed that there is net uplift).
- 2. The four AHUs have a total of 32 expansion anchors. The results of the bolt tightness check are: 16 tight, 4 loose but retorqued OK, 3 loose and cannot be retorqued, and 9 inaccessible.
Resolution: Design Change D1-95-080 was issued to replace isolator locknuts and repair the anchorage. 11 70RWC-2A Control Room Chillers Outlier issue: ORWG2B Anchorage: These two chiller units have the same anchorage: each is supported on 6 vibration isolators that are expansion anchored into an r/c floor stab. The isolators are designed to resist uphft and lateralloads, and the evaluation attached to the SEWS shows that, if properly installed, the isolators and their anchorage are adequate. The fans are outliers because:
- 1. The isolators are missing the locknut between the head of each isolator's adjustment bolt and the equipment skid. This locknut is required to prevent uplift (the anchorage evaluation showed no net uplift, but the SRT judged that it would be good engineering practice to install the locknuts).
- 2. The two chiller units have a total of 24 expansion anchors. The results of the bolt tightness check are: 8 tight,16 loose and cannot be retorqued.
Resolution: Design Change D1-95-080 was issued to replace isolator locknuts and repair the anchorage. i JAFNPP USl A-46 Seismic Evaluation Report f September 1995 page 24/38
V ( V Cl ID Description Outlier issue and Resolution 13 71UPS-1 Uninterruptable Bus Outlierissue: et Bounding Spectrum Caveats: This MG set is anchored on three vibration isolators. Each isolator is a 1.5" thick rubber pad with a threaded fitting on the top and a steel plate with two expansion anchors on the bottom. The anchorage analysis attached to the SEWS shows no net uplift on the isolators, but each isolator is subject to a shear load of about 1200 lbs. The SRT could find no basis to judge the shear load acceptable. Anchorage: The anchor bolts need to be bolt tightness checked. Resolution: Anchor bolts have been successfully checked (WR 95-06102-00). For the isolators, either test , the anchorage to show that it can take the required load, or install *' bumpers" to take the shear load. A bumper could consist of an angle with one leg expansion anchored to the floor stab, and the other leg abutting the skid. Leave a small gap between the angle and the skid (~1/4") and fill the gap with a rubber pad. 14 71BCB-2A Station Battery Control Outlier issue: BCB-2B Boards Anchorage: The two battery control boards have the same anchorage: each sits on two lengths of embedded steel, one along the front of the board, and one along the back. The boards are wekled to the embedded steel . in the front, but not to the embedded steel in the back (the boards are directly in front of an r/c wall, so the back is not accessible for welding). Resolution: Design Change D1-95-019 was issued to brace the top of the boards to the r/c wall.. 15 71 SB-1, 2 Station Batteries Outlierissue: 71 BAT-3A, 3B LPCI Batteries Bounding Spectrum Caveats: All of the batteries are 10 years old or more. The station batteries were installed in 1983, the LPCI batteries were installed in 1984/1985. Resolution: Both the station batteries and the LPCI batteries are maintained per IEEE 450-1987. Industry and NRC research indicates that maintenance per this procedure will maintain the cells' seismic integrity (Ref.10). 15 71SB-1 Station Batteries Outlier issue:
- 1. Bounding Spectrum Caveats: There are small gaps between the batteries and the enclosMa rails on the ,
back-to-back racks at the end of the room furthest from the door. The rails need to be frghtened.
- 2. Anchorage: The battery racks are anchored with 72 expansion anchors. Seven (7) of these bolts have gaps of greater than 1/4'.
Resolution: PID 59741 was issued for corrective maintenance work. Work was completed on 10/13/94 (WR 94-07901-00). JAFNPP USl A-46 Seismic Evaluation Report September 1995 page 25/38
- O O I
i Cl ID Description Outlier issue and Resolution
.l 16 711NV-38 LPCI inverter B Outlier issue: ' I Anchorage: There are spaces between the bottom of the inverter and the floor slab at some of the anchor bolt locations. These spaces are shimmed and/or grouted. The SRT judged that the shimming / grouting is only i marginally adequate - the grout is cracked or loose in a number of locations. I Resolution: Work Request WR 95-05040-00 was issued to repair the grouting. !
i 20 09-3 Main Control Boards Outlier issue: ; 09-5 Interaction: The control room has a suspended ceiling consisting of a rod-hung grid with aluminum egg-crate 09-6 ceiling panels. The grid support is judged adequate, but the egg-crate panels are not positively secured to the i grid. These types of panels are known to fall out in earthquakes - they're not heavy enough to damage the ' l paners structure, but they could strike switches on the benchboard or control room personnel, so they are l judged an interaction hazard. ; Resolution: Design Change D1-95-034 was issued on 5/18/95 to install plastic ties to secure the panels. .l; 20 09-32 RHR/RCIC Channel A, Outlierissue: ~ 09-45 Auto Blowdown, and Interaction: These three cabinets all contain essential relays and are bolted together. A nearby unanchored l 09-46 Core Spray Channel A storage cabinet could slide or tip and strike the cabinets. l Relay Cabinets ) Resolution: The storage cabinet was removed on 6/8/95. 20 09-95 Emergency Core Outlierissue: , 09-96 Cooling System Trip Interaction: These two cabinets both contain essential relays and are part of a row of adjacent cabinets. None Cabinets of the cabinets in the row are bored together. [ Resolution: PIDs 60037 (WR 95-03859-00) and 60039 (WR 95-03860-00) were issued for corrective maintenance work. ! 20 27 CAD Containment Air Outlier issue Dilution Panel Interact #on: 27 CAD contains essential relays and is not bolted to the abutting cabinet 27PCP. l Resolution: PID 60042 (WR 95-03863-00) was issued for corrective maintenance work. j 20 71UPP Uninterruptable Bus Outlier issus: MG Set 71UPS-1 Anchorage: A bolt tightness check is required. ! Control Panel , Resolution: A bolt tightness check was performed successfully (WR 95-06101-00). ; JAFNPP USI A-46 Seismic Evaluation Report [ September 1995 i page 26/38 l i t I
l l l (
) 3.4 Seismic Demand for Essential Relay Cabinets l During the walk downs, the SRT established the cabinet amplification factor for use with the Level 2 relay l screening method (GlP Section 6.4.2). The amplification factors were based on the requirements of GIP l Table 6-2 and Appendix i of EPRI NP-7148 (Reference 11). The SRT documented their selection in the l notes section of the cabinets' SEWS (Appendix G).
Table 3.4 summarizes this effort. The first four columns of Table 3.4 lists the cebinets that contain essential relays (from Reference 3, Attachment F) and their location. The fifth column lists the l amplification type determined by the SRT - HIGH, MEDIUM, or LOW as specified in GIP Table 6.2. Four switches were designated RIGID (These switches are bolted on Unistruts which directly anchored to a reinforced concrete wall, and the SRT judged that no significant amplification of the floor response spectrum would occur). The sixth and seventh columns contain the seismic demand on the relays in l each cabinet. The Peak Demand is the demand in the frequency range from 4 Hz to 16 Hz. The ZPA l Demand is the demand at and above 33 Hz. These values are used for the seismic screening of essential relays in Reference 3. l The Peak and ZPA demands were determined as follows: j l
- 1. Table 3.3 lists all floor elevations that contain cabinets housing essential relays, and the peak and ZPA of the corresponding horizontal,5% damped floor response spectra (FRS). The peak of the FRS is the peak value between 4 Hz and 16 Hz of both the EW and NS FRS. The ZPA of the FRS is the peak value at or above 33 Hz of both the EW and NS FRS. The last row of Table 3.3 lists the i peak and ZPA of 2.25x the 5% damped SSE. GIP Table ti.1 specifies this as an attemative FRS for cabinets mounteri below about 40' above grade and having c natural frequency greater than 8 Hz.
[ 2. For MCCs, the Peak and ZPA Demands in Table 3.4 were calculated by multiplying the (],/ corresponding FRS peak and ZPA values by 3, the LOW amplification factor specified for MCCs.in GIP Table 6-2. All the MCCs listed in Table 3.4 were judged by the SRT to have fundamental frequencies less than 8 Hz, so the attemative 2.25x SSE FRS could not be used.
- 3. All other cabinets listed in Table 3.4 were judged by the SRT to have fundamental frequencies greater than 8 Hz, and all their locations are within about 40' of grade, so the alternative 2.25x SSE FRS could be used. The attemative FRS is lower than the actual FRS at all locations except the relay room (RR 284.67). All cabinets in the relay room were designated MEDIUM. so the demand values were calculated by multiplying the relay room FRS values by 4.5 (MEDIUM factor per GlP Table 6.2). For cabinets outside the relay room, the alternative 2.25x SSE FRS values were multiplied by either 7 (HIGH),4.5 (MEDIUM), or 1 (the four switches designated RIGID).
Table 3.3 Floor Response Spectra Values Location Peak (4-16 Hz) ZPA (Peak >33 Hz) EG 272.00 0.30 0.53 RB 242.00 0.87 0.20 RB 272.00 0.87 0.20 RB 300.00 1.07 0.31 RR 284.67 0.43 0.22 2.25
- SSE 0.53 0.34 EG: Emergency Diesel Generator Area RB: Reactor Building RR: Relay Room
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JAFNPP USI A-46 Seismic Evaluation Report September 1995 page 27/38
l 1 Table 3.4 Seismic Demand for Cabinets Containing Essential Relays O I Cabinet Demand ID Description Location Type Peak ZPA j 1 09-32 CHAN A RHR/RCIC RELAY PNL RR 284.67 Medium 1.9 1.0 l
~2 09-33 CHAN B RHR/RCIC RELAY PNL RR 284.67 Medium 1.9 1.0 I 3 09-39 HPCI RELAY PNL RR 284.67 Medium 1.9 1.0 I 4 09-45 AUTO BLOWDOWN RELAY CAB RR 284.67 Medium 1.9 1.0 l 5 09-46 CORE SPRAY CHAN A RELAY CAB RR 284.67 Medium 1.9 1.0 6 09-47 CORE SPRAY CHAN B RELAY CAB RR 284.67 Medium 1.9 1.0 7 09 95 EMERG CORE COOLING SYS DIV 1 A/C TRIP CAB RR 284.67 Medium 1.9 1.0 8 09-96 EMERG CORE COOLING SYS DIV 2 B/D TRIP CAB RR 284.67 Medium 1.9 1.0 )
9 09AR 5A (RED) A AUXILIARY RELAY CAB RR 284.67 Medium 1.9 1.0 J 10 09AR-5B (BLUE) B AUXILIARY RELAY CAB RR 284.67 Medium 1.9 1.0 j 11 10DPIS-125A RHR A DIFF PRESS INDIC SWITCH RB 242.00 Medium 2.4 1.5 12 10DPIS-1258 RHR B DIFF PRESS INDIC SWITCH RB 242.00 Medium 2.4 1.5 13 15PS-122A RBCLC PUMPS DISCH HDR PRESS SWIiCH RB 300.00 Rigid 0.53 0.34 14 15PS-1228 RBCLC PUMPS DISCH HDR PRESS SWITCH RB 300.00 Rigid 0.53 0.34 15 15PS-122C RBCLC PUMPS DISCH HDR PRESS SWITCH RB 300.00 Rigid 0.53 0.34 16 15PS-122D RBCLC PUMPS DISCH HDR PRESS SWITCH RB 300.00 Rigid 0.53 0.34 , 17 25-50 HPCllNST RACK RB 242.67 High 3.7 2.4 ! 18 27 CAD CONTAINMENT AIR DILUTION PNL RR 284.67 Medium 1.9 1.0 19 71BMCC-2 RB EAST CRESCENT DC MCC RB 242.67 Low 2.6 0.6 20 71 BMCC-4 RB EAST CRESCENT DC MCC RB 242.67 Low 2.6 0.6 l 21 71 BMCC-6 RB DC MCC RB 272.00 Low 2.6 0.6 j 22 71H05 4160V SWITCHGEAR DISTRIBUTION (BUS 10500) EG 272.00 High 3.7 2.4 ' 23 71H06 4160 SWITCHGEAR DISTRIBUTION (BUS 10600) EG 272.00 High 3.7 2.4 Q 24 25 71MCC-152 71MCC-153 600V MCC (BUS 115200) 600V MCC (BUS 115300) RB 272.00 RB 242.67 Low Low 2.6 2.6 0.6 0.6 I 26 71MCC-155 600V MCC (BUS 115500) RB 242.67 Low 2.6 0.6 27 71MCC-161 600V MCC (BUS 116100) RB 272.00 Low 2.6 0.6 28 71MCC-163 600V MCC (BUS 116300) RB 242.67 Low 2.6 0.6 29 71MCC-165 600V MCC (BUS 116500) RB 242.67 Low 2.6 0.6 30 71MCC-254 600V MCC (BUS 125400) EG 272.00 Low 0.9 1.6 31 71MCC-264 600V MCC (BUS 126400) EG 272.00 Low 0.9 1.6 32 93AURP-01 EDG A & C AUX UNDERVOLTAGE RELAY PNL EG 272.00 Medium 2.4 1.5^ 33 93AURP-02 EDG B & D AUX UNDERVOLTAGE RELAY PNL EG 272.00 Medium 2.4 ES 34 93ECP-A EDG A ENGINE CONTROL PNL EG 272.00 High 3.7 2.4 35 93ECP-B EDG B ENGINE CONTROL PNL EG 272.00 High 3.7 2.4 36 93ECP-C EbG C ENGINE CONTROL PNL EG 272.00 High 3.7 2.4 37 93ECP-D EDG D ENGINE CONTROL PNL EG 272.00 High 3.7 2.4 38 93ECSP-A EDG A ENGINE CONTROL SUB PNL EG 272.00 Medium 2.4 1.5 39 93ECSP-B EDG B ENGINE CONTROL SUB PNL EG 272.00 Medium 2.4 1.5 40 93ECSP-C EDG C ENGINE CONTROL SUB PNL EG 272.00 Medium 2.4 1.5 41 93ECSP-D EDG C ENGINE CONTROL SUB PNL EG 272.00 Medium 2.4 1.5 42 93EGP-A EDG A GENERATOR CONTROL PNL EG 272.00 High 3.7 2.4 43 93EGP-B EDG B GENERATOR CONTROL PNL EG 272.00 High 3.7 2.4 44 93EGP-C EDG B GENERATOR CONTROL PNL EG 272.00 High 3.7 2.4 45 93EGP-D EDG B GENERATOR CONTROL PNL EG 272.00 High 3.7 2.4 46 93FPAC EDG A & C FORCED PARALLELING PNL EG 272.00 Medium 2.4 1.5 47 93FPBD EDG B & D FORCED PARALLELING PNL EG 272.00 Medium 2.4 1.5 m U JAFNPP USI A-46 Seismic Evaluation Report September 1995 < page 28/38 f i
r ! 4. Tanks and Heat Exchangers Review l 4.1 Summary of the Review The tanks and heat exchangers reviewed as part of the A-46 effort are listed in Table 4.1. The table also contains a summary of the evaluations. The detailed tank evaluations, including field notes, sketches, photographs, and calculations are included with the SEWS in Appendix G. l l JAFNPP USI A-46 Seismic Evaluation Report September 1995 page 29/38
f A L U J Table 4.1 Summary of Tank Evaluations ID Description Evaluation Summary 03TK-1A SCRAM Discharge Small vertical tanks (8.5* tall,24" diameter,1.2" thick ) supported on 4 substantial wide-flange legs. The legs are 03TK-1B Instrument Air Volume welded to a well stiffened base plates anchored with 16 (Tank A) and 14 (Tank B) 1.25" Hilti expansion anchors. Tanks The SRT judged the tanks themselves adequate by inspection. The capacity of the anchorage exceeds the demand imposed by the tanks' seismic inertial loads by about a factor of 7 (the SRT made the observation that the design of the anchorage is probably controlled by the hydrodynamic loads imposed during the SCRAM event). 10E-2A RHR Heat Exchangers Vertical heat excWngers approximately 20' tall and 5' in diameter. At mid-height, each heat exchanger is attached to 10E-2B a very substantial steel ring support with twelve (12) 2" diameter bolts. There is an additional engineered lateral support near the top. The SRT judged the heat exchangers and their supports adequate by inspection. 11TK-1 Standby Liquid Control A 9' diameter,11' tall, 3/16" thP;k flat-bottom vertical tank anchored with 121" cast-in-place bolts. There are no bolt Tank chairs - each bolt secures a 12" wide, 3" deep,1" thick steel fitting which clamps the bottom plate of the tank. The evaluation attached to the SEWS shows that the tank meets the requirements of Section 7 of the GIP with the anchorage remaining in the elastic range. The bending stress in the bottom plate at the clamp is about 70% of yield, the tensile load in the bolt (including the effects of prying action) is about 40% of the GIP allowable, and the compressive stress in the tank is essentially negligible. Note that the tank radius is 4.5', which is slightly below the range in GlP Table 7-1 (5' to 35'), but as all other parameters all well within range and the margin is substantial, this was judged acceptable. 27E-1A Containment Air Small, planar, liquid-to-air heat exchangers that are U-bolted to a steel angle frame which is welded to the liquid 27E-1B Dilution (CAD) Ambient nitrogen tank (27TK-7A and B). Heat Exchangers The SRT judged them adequate by inspection. Note that the liquid nitrogen tanks were evaluated separately; these heat exchangers could have been considered " rule-of-the-box" with the tanks. 27NV-9A Containment Air 36" wide x 44" deep x 88" tall vertical liquid-to-air heat exchangers, each bolted to building steel at the base with 27NV-98 Dilution (CAD) Ambient four (4) 1/2" bolts at each comer. Vaporizers The heat exchanger is well constructed - the SRT judged that only the anchorage need be checked (this is consistent with the approach in Section 7 for liquid-to-liquid heat exchangers). The bolts connecting the heat exchangers to the building steel were explicitly analyzed - the ratio of seismic capacity to seismic demand was conservatively calculated as 1.6. JAFNPP USl A-46 Seismic Evaluation Report September 1995 page 30/38
- = . .. . - . .
b O O O ID Description Evaluation Summary i i 27TK-7A Containment Air Each of 27TK-7A and 7B consists of two horizontal cylindrical tanks, one inside the other, connected at the ends by 27TK-7B Dilution (CAD) Liquid a fiberglass shaft setbng in steel couplings, The extemal tank is 7.5' in diameter and 25' long, the inside tank is T in Nitrogen Tanks diameter,24' long, and is full of liquid nitrogen. The outer tank is welded to a pair of steel saddles; each saddle is
- anchored to a concrete pier with two (2) 13/8" cast-in-place bolts.
The tank, saddle, anchor bolts were evaluated per the procedure for horizontal tanks and heat exchangers in Section 7 of the GlP. The evaluation showed a seismic capacity of 0.31g versus a seismic demand of 0.20g. The , saddles and piers were evaluated and found adequate. The fiberglass shaft connectmg the inner and outer tanks was found adequate based on load tests contained in the vendor documentation 29AC-1 A thru H MSIV Air Accumulators These are 30" long,15" diameter air accumulator tanks welded to two steel saddles. On the inboard side, the , saddles are well welded to building steel. On the outboard side, the saddles are anchored to r/c walls with four (4) _ j 1/2" expansion anchors. The tanks were tug tested and found secure. The tubing running from the accumulators to the MSIVs was inspected and judged - 9; :s:_4. The SRT judged the tanks adequate by insym,uun. 33TK-12A Condensate Storage A pair of vertical flat bottom tanks, each with an overall height of 36'-3" (including the dome) and 34'-0" in diameter. 33TK-12B Tanks Each tank is anchored with twelve (12) equally spaced 1.5" cast-in-place bolts. The tanks are founded 1T-9" below grade. The section of each tank below grade is surrounded by 1" of fiberglass insulation, then a 15" thick r/c wall, and finally structural backfill and rock. Because of the insulation (which is assumed to be flexible), the tanks are analyzed as cunis/,/ :j freestanding a , The tanks were analyzed per GIP Section 7 and met those requirements with the following notes:
- 1. The overtuming margin (Mcap/Mdem) is 1.16. The base shear margin (Ocap/Qdem) is 3.2. The freeboard margin (hf/hs)is 4.0.
- 2. Table 7.1 of the GIP requires that t/R (tank wall thickness to tank radius) be > 0.001. For this tank t/R = 0.00092.
The SRTjudged this discrepancy wpu== . a '! l
- 3. The width of the side plates on the bolt chairs is 0.375". The GIP requires that this width be at least 0.5" (see Step 10 in GIP Section 7). This requirement is one of three requirements that must be met and are intended to ,
ensure that the side plates do not buckle under the bolt load. The 0.5" requirement is a fairly arbitrary design guidelme; the other two requirements are actually check the stability and stress levels in the plates: k/j < 95/SQR(Fy) -> 6/0.375 < 95/SQR(30)-> 16 < 17.3 j JAFNPP USI A-46 Seismic Evaluation Report September 1995 page 31/38
- - _ _ - . . _ . . _ _ _ = _ - _ _ _ _ _ _ _ _ - - __ - _ _ - ___ _ _ _ _ . _ _ _ - _ _ - _ _ _ - _ . .___-_a
O O O ID Description Evaluation Summary Pu/2kj < 17.5 ksi -> 31.2/2x6x0.375 < 17.5 -> 6.9 < 17.5 The first of these two requirements ensures that the plates won't buckle (this is simply the AISC requirement for unstiffened elements subject to compression such as compression flanges of beams), and the second requirement keeps the stress level below 0.6Fy. As this bolt chair meets both requirements it is reasonable to conclude that the chair side plates are adequate. 39ACC-256A, B, MSRV Air These are each an 18" length of 4" Sch 40 pipe welded to a pair of saddles and bolted to building steel with four 1/2" C, D, E, G, H, J, Accumulators bolts. The SRT judged them adequate by inspection. K and L 93AR-A1 to A10 EDG Air Start Receiver There are 40 identical air start receiver tanks,10 in each diesel bay. The tanks are 24"in diameter,45.5" tall, and 93AR-B1 to B10 Tanks supported on 3 angle legs rising 6" above the floor. Each tank weighs 375# and its C.G. is 29" above the floor. 93AR-C1 to C10 Each leg is anchored into the concrete with a single 1/2* or 3/8" expansion anchor. All bolts were inspected and 93AR-D1 to D10 tightness checked - the inspection is documented on the form attached to the SEWS for each tank. The SRTjudged the tanks adequate by inspection. The anchorage was evaluated per the requirements of GlP j 11.4.2 and Appendix C and found adequate. 93TK-6A EDG Fuel Oil Storage Four (4) 12' diameter,45' long horizontal steel tanks (A285 Grade C) buried in two vaults below and adjacent to the 93TK-6B Tanks diesel generator building. The vaults, each of which is big enough to fit two tanks (the A, C and the B, D tanks each 93TK-6C share a vault), was excavated out of rock and lined with an r/c wall. Each tank is anchored with four 1/2" x 3" hold-93TK-6D down straps and eight 12' long rock anchors. The vaults are filled with structural backfil1. i About 6' of the east end of the each tank is directly under the diesel generator building. There is a 25" diameter,55" long manhole that leads from the top of each tank into the diesel generator rooms. The fuel piping is inside this manhole. As the tank vaults are essentially integral with the diesel generator building and both are founded on rock, the SRT judged the tanks and fuel piping not seismically vulnerable. . JAFNPP USI A-46 Seismic Evaluation Report September 1995 page 32/38
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i i i ID Description Evaluation Summary - 93TK-7A EDG Fuel Oil Day Four small horizontal tanks on saddles. Each tank has a capacity of 545 gal, weighs 5910 lbs full, and is supported ' 93TK-7B Tanks on two saddles. Each saddle is anchored into a concrete piers with 4 - 7/8" diameter cast in place bolts. 93TK-7C . l' 93TK-7D The anchor bolts are 3.25" from the long edge of the pier and 6" from the short edge of the pier. Both edge . . distances are less than the GIP Table C.3-1 minimum of 7.75", and the 3.25" distance is 0.25" less than the outlier limit of 4 bolt diameters (3.5"). The tank was analyzed (per GIP Sechon 7 procedures) assuming 3/4" bolts (which would meet the edge distance requirements) and shown to be satisfactory (margin of 0.768 / 0.588 = 1.3). This t evaluation is conservative for the following reasons-l
- 1. The pullout capacity of the anchsisge is govemed by the base plate bending capacity (Step 3 in the GIP Section i 7 procedure). This makes the edge distance issue moot for pullout capacity.
- 2. For a given direchon of shear only half of the anchors are loaded in the direchon of the edges, the other anchors I are loaded away from the edges and have full capacity Furthermore, this is a small tank that sees little temperature -!
variabon, so neither saddle has slotted bolt holes, thus the actual capacity in the longitudinal direchon is more than ! twice that assumed in the analysis. : i
- 3. The anchors are inside the pier's rebar cage which consists of 5 #6 vertical dowels along each long face tied ,
together with 2 horizontal stirrups (#4s) near the top of the bolts and another stirrup near the bottom i A "more correct" approach may be to perform the analysis using the actual 7/8" bolts and ignoring the edge distance ; knockdowns. This evaluabon was also done; it yielded a margin of 2.275 / 0.588 = 3.9. l l The saddle stresses were also checked and found to be low. Based on the above, the SRT judged the anchorage adequate despite the edge distance issue. t i t i JAFNPP USI A-46 Seismic Evaluation Report ; September 1995 I page 33/38 - 3
\ . 4.2 Summary of Outliers No outliers resulted from the tanks and heat exchangers review.
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JAFNPP USI A-46 Seismic Eva;uation Report September 1995 page 34/38
- o. 5. Cable and Conduit Raceway Review L) 5.1 Summary of the Review The raceway review was performed as specified in GIP Section 8. Raceway systems were walked-down, checked against the inclusion Rules and Other Seismic Performance Concerns as specified in Section 8.2 of the GIP, and examined for seismic spatial interactions with adjacent equipment and structures. Ten (10) representative, worst-case raceway supports were selected and as-ouilt. These supports then received a Limited Analytical Review per GIP Section 8.3 of the GlP. Outliers were identified and documented.
This section (Section 5.1) summarizes the raceway review. The scope of the review is described in Section 5.2. Section 5.3 contains the results of the Limited Analytical Reviews (LARs). Section 5.4 summarizes the raceway outliers. The Plant Area Summary Sheets (PASS) are in Appendix C. The calculations performed for the Limited Analytical Reviews (LARs) are in Appendix D. Outlier Seismic
- Verification Sheets (OSVS) are included in Appendix E.
- 5.2 Scope of the Review The scope of the review was determined by studying the plant layout drawings and walking through the plant to determine how cabling is routed to the areas of the plant containing the Safe Shutdown Equipment List (SSEL) equipment. Based on this, the review included all cable and conduit raceway systems in the
+ areas of the plant where equipment on the Safe Shutdown Equipment List (SSEL)is located, plus the , cable spreading room and the cable tunnels. i The walk down of each plant area was documented on a PASS. Table 5.1 summarizes the PASS, The first column contains the ID used to track the PASS, the second column describes the area of the plant g3 covered by the PASS, and the third column lists the LARs (if any) associated with the PASS. The PASS , themselves - including the checklists, SRT notes, photographs, and LAR as-builds - are in Appendix C. Table 5.1. Summary of the Plant Area Summary Sheets (PASS) PASS # Plant Area LAR # RACE 001 East and West Crescents LAR001
- RACE 002 Toms
! RACE 003 Reactor Building 272 LAR002 RACE 004 Reactor Building 300
- RACE 005 Reactor Building 326
- RACE 006 Reactor Building 344 RACE 007 Cable Tunnels 260 LAR003, 4, 5 RACE 008 Cable Tunnels 286 RACE 009 Electrical Bay RACE 010 Emergency Diesel Generator Area LAR006 RACE 011 Service Water Pump Area RACE 012 Battery Rooms J RACE 013 Cable Spreading Room LAR007 RACE 014 Relay Room LAR008, 9,10 RACE 015 Control Room RACE 016 Control Room A/C Area RACE 017 CAD Building RACE 018 Drywell and Main Steam Tunnel +
;V JAFNPP USl A-46 Seismic Evaluation Report September 1995 page 35/38
__ _ y i I l lr 5.3 Limited Analytical Reviews (LARs) j The Limited Analytical Reviews (LARs) evaluate the seismic capability of the raceway supports which'were selected as representative, worst case examples of the major types of raceway support configurations i 4 within JAFNPP, Ten (10) supports were selected for evaluation. The evaluations were performed per the f guidelines in GlP Section 8.3. j l Table 5.2 summarizes the LARs. The first column lists the ID used to track the LARs. The second column contains a brief description of the subject raceway support. The third and fourth columns contain.the l 4 goveming interaction value and associated load case for the LAR (The interaction value in the third column ; is the ratio of a computed value to an allowable value, so an interaction value of less than one (1) indicates that the computed value is less than the allowable). , Table 5.2 Summary of the Limited Analytical Reviews i
; LAR # Support Description interaction Load Case ,
LAR001 Location: : Reactor Building Crescents 0.43 Dead Load Wall bracket, three tiers, Unistrut construction, anchored with expansion anchors. ; LAR002 Reactor Building Elevation 272 1.45 Dead Load (Outlier) { 3/4" threaded rod trapeze, seven tiers, bolted to 2.56 3x Dead Load l Unistrut runner spanning between embedded j Unistruts in the ceiling. l LAR003 Cable Tunnels, Elevation 260 0.41 Dead Load 3/4" threaded rod trapeze,6 tiers, anchored with 0.64 3x Dead Load 3/4" shell anchors. LAR004 Cable Tunnels, Elevation 260 0.41 Dead Load (Outlier)- O 3/4" threaded rod trapeze,6 tiers, anchored by bolting into embedded Unistruts. 1.13 3x Dead Load LAR005 Cable Tunnels, Elevation 260 0.41 Dead Load i Wall bracket with 3/4" threaded rod vertical ] support at free end,6 tiers, bolted to embedded Unistrut LAR006 EDG Area, Elevation 272 0.40 Dead Load l 3/4" threaded rod trapeze, 3 tiers, bolted to 0.70 3x Dead Load Unistrut spanning between roof beams. LAR007 Cable Spreading Room, Elevation 272 0.55 Dead Load Floor-to-ceiling Unistrut frame,7 tiers, beam- 0.49 3x Dead Load clamped to building steel at the top, expansion 0.51 Lateral Load anchored to r/c slab at the bottom. LAR008 Relay Room, Elevation 286 0.41 Dead Load Wall bracket with 3/4" threaded rod vertical support at free end, 9 tiers, expansion anchored to r/c wall. LAR009 Relay Room, Elevation 286 0.41 Dead Load 3/4" threaded rod trapeze, 5 tiers, one rod 0.73 3x Dead Load expansion anchored to r/c ceiling, other rod beam clamped to building steel. LARO10 Relay Room, Elevation 286 0.50 Dead Load 3/4" threaded rod trapeze, 5 tiers, beam clamped 0.88 3x Dead Load to building steel. ; O JAFNPP USl A-46 Seismic Evaluation Report i September 1995 page 36/38 i
- - - - . _ . _ . --- I
1 l l 5.4 Summary of Outliers Q,a A total of two (2) outliers resulted from the cable and conduit raceway reviews. A description of each raceway outlier and its resolution is provided in Table 5.3. 1 Table 5.3 Raceway Outliers 1 ID Location Outlier issue and Resolution ) PASS # RACE 003 Reactor Building 272' Outlier issue l LAR# LAR002 ! An enveloping hanger in the northwest region of Reactor Building 272 was chosen for limited analytical review. The hanger is a 3/4" rod hung trapeze supporting seven trays. : The hanger is anchored by bolting into a Unistrut P1000 1 which spans between embedded Unistruts in the r/c ceiling. l The bending moment in the P1000 exceeds allowables for j the dead load check and the vertical capacity check (3x ' dead load). Resolution 1 l Design Change D1-95-107 and WR 95-06585-01 were . issued to reduce the moment in the P1000 by installing an l expansion anchor at or near the point of maximum moment. i This fix was applied to the subject hanger and five other similar hangers in the area. In addition, an action plan has been intiated to identify any other hangers of similar [,h construction that may require modification. N! l PASS # RACE 007 Cable Tunnels Outlier issue LAR# LAR004 Elevation 260' An enveloping hanger in the cable tunnels (Turbine Building 260')was chosen for limited analytical review. The hanger is a 3/4" rod hung trapeze supporting six trays. The hanger is i anchored by bolting into embedded Unistruts in the r/c ceiling. The hanger exceeds allowables for the vertical capacity check (3x dead load) due to the loads on the embedded Unistrut. Resolution Per GIP Section 8.4.8, a limit state evaluation was performed which showed that the maximum load in the embedded strut that could be developed is less than allowables (the limit state evaluation is included with the limited analytical review in Appendix D). I O' JAFNPP USl A-46 Seismic Evaluation Report September 1995 l page 37/38
p 6. References V 1. Seismic Qualification Utility Group (SQUG), " Generic implementation Procedure (GIP) for Seismic Verification of Nuclear Plant Equipment" Revision 2, corrected February 14,1992.
- 2. USNRC, " Supplement No.1 to Generic Letter (GL) 87-02 that Transmits Supplemental Safety Evaluation Report No. 2 (SSER No. 2) on SQUG Generic Implementation Procedure, Revision 2, as Corrected on February 14,1992 (GIP-2)," dated May 22,1992.
- 3. Engineering and Planning Management, Inc. "New York Power Authority James A. FitzPatrick Nuclear Power Plant Safe Shutdown Equipment and Relay Evaluation for Unresolved Safety issue (USI) A-46", Final Report, September 1995
- 4. Letter from R. E. Beedle (NYPA) to USNRC dated 9/22/92, " Response to Supplement No.1 to Generic Letter 87-02..." (IPN-92-043 / JAFNPP-92-053)
- 5. Letter from Brian C. McCabe (USNRC) to R. E. Beedle (NYPA) dated 11/17/92, " Response to Supplement No.1 to Generic Letter 87-02. . James A. Fitzpatrick Nuclear Power Plant"
- 6. UFSAR, James A. FitzPatrick Nuclear Power Plant
- 7. Stone and Webster, " Final Report on USNRC IE Bulletin No. 80-11, Masonry Walls, James A .
FitzPatrick Nuclear Power Plant", March 15,1982, Fiche 3078 Frames 160-168
- 8. Stone and Webster, " Report on USNRC IE Bulletin No. 80-11 (180 Day Response), Masonry Walls, James A . FitzPatrick Nuclear Power Plant"., Nov 3,1982, Fiche 965 Frames 182-216 and DCC Batch 965
- 9. General Electric Industrial Controls Products Department Report No. 75lCS001 A, " Vibration Testing and Analysis of 7700 Line AC Motor Control Centers",10/25/75.
- 10. EPRI TR-1100248, Final Report, Dec 1992, " Stationary Battery Maintenance Guide" v 11. EPRI NP-7148, " Procedure for Evaluating Nuclear Power Plant Relay Seismic Functionality",
December 1990
- 12. EPRI TR-102180, Project 2925-02, Final Report, March 1993, " Guidelines for Estimation or Verification of Equipment Natural Frequency" i
h Q ) JAFNPP USl A-46 Seismic Evaluation Report j September 1995 ; page 38/38 l i
. - . _- . . = _ . .. .- .. . _ - -. .
l l i I Appendix A - Resumes of the Seismic Capability Engineers This appendix contains the SQUG certificates and resumes of all of the Seismic Capability Engineers who i participated in this project: Arun Pal (New York Power Authority) , Doug Huwe (New York Power Authority) ! Frank Stille (Stevenson & Associates) l Mara Lakis (New York Power Authority) ! Pritt Okas (New York Power Authority) Robert Kester (New York Power Authority) Stephen Anagnostis (Stevenson & Associates) , Walter Djordjevic (Stevenson & Associates) l l l l JAFNPP A-46 Seismic Evaluation Report September 1995 Appendix A
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__, David A. Freed. MPR Associates j SQUG Training Coordinator SQUG Program Manager i es= m _ - -- 1
i a l Arun C. Pal 33 Melanie Manor, East Brunswick, N.J. 08816 l O ! EDUCATION B. Tech. (Hons.) in Civil Engrg. -Indian Inst. of Tech. India. I M.S. in Civil Engrg. - Brooklyn Polytechnic, N. Y. Post-Graduate Diploma in indl. Psychology & Indl. Relations Engineer Degree in Energy Systems - The George Washington U.,D.C. PROFESSIONAL AFFILIATIONS Registered Professional Engineer (P. E.) in N.J., Md., D.C. & N. Y. (applied) i Member, Am. Society of Civil Egrs. (ASCE) - Nuclear Energy Comm. Member (former) Safety Tech. Task Force of The Elect. Power Researti inst, i Program Manager and Memberof ESEERCO-Seismic Monitoring Network i NON DEGREE SHORT COURSES ( Technical Subject Matters ) N SQUG/EPRI Courses For USI A-46 & IPEEE : Equipment Selection, SQUG Walkdown & IPEEE Add-on Courses. Theory of Plates and Shells- Bechtel Fracture Mechanics- Union College Grouting Fundame.ntats- U. of Missouri Design of Welded Structures- Lincoln Electric Co. Pipe Supports Design- NPS Fossil Fueled Power Plants- Bechtel Non-Technical / Management Courses Engineering Services in Dewloping Countries - ASCE Process of Management & Motivation WeiirJ+ Potomac Elet. Power Co. Proj. Mgmt. & Root Cause Anal. for Org. and Prog. Improwment- NYPA Effective Writing & Technical Presentation - NYPA O
TECHNICAL PAPERS (in chronological orde_r)
- Seismic Analysis & Design of Nuclear Power Pllants-10th World Conf. on Earthquake O Engineering, July 1992, Madrid, Spain.
- Spent Fuel Cask Handling at an Operating Nuclear Power Plant, ANS Power Div. Topical Meeting, April 1988, Myrtel Beach,S.C., U.S.A.
- Evaluation of an Existing Spent Fuel Pool for Storage of Consolidated Fuels, Coeuyhored with G.A. Harsted et. al., 9th SMIRT Conf., Aug.1987, Lucrne, Switzerland.
- Seis; .2/ Dynamic Fragility and Systems intraction Study at Indian Point, Aug.,198S, Brookhaven Nati. Lab., N.Y., (NUREG/CP-0070)
- Seismic Design Criteria for Fossil Power Plants, Energy 84, sponsored by ASCE Energy Comm. , Pasadena, Calif.
- Tchnology Assessment of Distributed Photovoltaics,3rd. Intl. Conf. on Alternative Energy, 1979, Miami,FI UNPUBLISHED PAPERS (for Energy Systems Program)
- Environmental Requirements for Fossil Power Plants
- Tidal Energy : Some Discrete ideas.
- The Use of PRA in Nuclear Power Plant Regulations..
EXPERIENCES 10/81 to Present at The N.Y. Power Authority as Sr. CiviVStnJctural Engineer. This is an in-house staff position performing tasks othenmse to be done by outside consultants. Duties include analysis and design of steel and concrete structures and components, equipment qualification and procurement, construction supervision at the sites and resolutions of site problems, presentation to regulatory bodies for approvals of modifications, review of work performed by A/Es etc. Responsible for communication with and management of designers, A/Es, vendors etc for inststellation of safe and most economical modifications. 6/78 to 9/81 at Potomac Electric Power Company, Washington,D.C. as Systems Engineer , Civil / Structural Engineering. Was responsible for the Civil /Stuctural Engineers and Designers involved in analysis, design and evaluations of exiting fossil fueled power plants to facilitate operation and maintenance. The total capacity was 6S00MW for 6 plants. O
' 2/74 to 5/78 at the Bechtel Power Corp., Gaithersburg, Md. as Sr. Engr. Was involved in cnalysis end design of concrete and steel structures and pipe and conduits and cable tray
- supports at Davis Basse Nuc. Power Plant , Unit No.1.
Prior year worked at Burns and Roe as a Designer for fossil plant . 6/71 to 3/73 at W. J. Barney Corp., a N.Y. City Gent. Contractor as Enrg, aide. 5/13/1971- migrated to The U.S. A. O O
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i DOUGLAS K. HUWE l l RD = 5 Box 124 l 1 Oswego, New York 13126 ' 4 (315)343-2526 ! EDUCATION Bachelor of Science in Civil Engmeermg ;
- South Dakota School of Mines and Technology ,
Rapid City, South Dakota, May 1981
- CAREER Fourteen years experience in the design, construction,
SUMMARY
and operation of mechanical and piping systems for process and power industries. i
- . EXPERIENCE Sr. Plant Eneineer, New York Power Authority,
- - 12/86 to present James A. Fitzpatrich Nuclear Power Plant.
4 Responsible for providing engineering expertise in the areas of plant design and modifications. j Provide technical assistance and direction to plant i operating, maintenance, and construction departments. { Perform detailed structural calculations and designs. Initiate new procedures and perform extensive revisions ' to existing plant procedures. Provide day-to-day supervision of contractor personnel assigned to the
- civil / mechanical group.
5/84- 12/86 Sr. Field Engineer. Stone & Webster Engineering jv Corporation, Nine Mile Nuclear Station Unit 2.
. Responsible for providing engineering support for ,
the installation of mechanical systems at NMP2 - i during construction. Initiated and coordinated field
- and engineering requested changes of piping, pipe supports, tubing, and instrumentation. Provided
, technical direction to other disciplines for the resolution ! 1 of field interferences that impaired installation to the
- original design requirements.
7/81-5/84 Construction / Pine Stress Eneineer. Fluor Engineers and Constructors, Inc. Responsible for i performing stress analysis on complex piping i systems utilizing both manual and computer-aided i techniques in the analysis of thermal expansion,
- internal pressure, wind, settlement, seismic i anchor movement, static seismic and dynamic
! seismic loading conditions. Evaluated piping loads and mechanical equipment nozzle connections. Designed special pipe support elements, snubbers, , and flexible hose connections. REGISTRATIONS Engineer-in-training, No. E-3379, South Dakota , A Available upon request.
, g REFERENCES I
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l l l FRANK B. STILLE O l EDUCATION: B.S.C.E. - Syracuse University - 1957 1 i M.S.C.E. - Syracuse University - 1961 SQUG Walkdown Screening and Seismic Evaluation Training Course - 1993 i REGISTRATION: l Commonwealth of Massachusetts - License No. 23071 4 PROFESSIONAL HISTORY: Stevenson & Associates Inc., Wobum Massachusetts,1993 i Northern States Power Company / Prairie Island Nuclear Generating Plant, Nuclear Projects Department- Consulting Engineer, 1992-1993 (q g Teledyne Engineering Services, Waltham Massachusetts - Engineering Services Manager,. Project Manager, Civil and Mechanical Engineer, 1974 -1992 1 i
' Aerospace Industry,1957 -1974 PROFESSIONAL EXPERIENCE:
Mr. Stille has nineteen years experience in the Civil / Structural / Mechanical Engineering of large nuclear power generation facilities. His experience covers: 1) direct performance of Civil and Mechanical Engineering; 2) project management of power plant design modification projects; and,
- 3) management of engineering, design and drafting services for an architect - engineering firm. His current work at Stevenson & Associates has included participation in several A-46 / IPEEE projects and the performance of a Q.A. verification of a general purpose finite element program. j l
He spent 15 months at a two unit nuclear power generetion plant as a Civil / Mechanical engineering I consultant. During this period he performed a second level review of an A/E's pipe stress and pipe l support design modifications for a larg e intake Cooling Water Header replacement project as the utility - representative. His responsibilities also included the provision of new support design, weld control - records, and field support to construction. His services to the utility also included participation on the Auxiliary Building Crane Upgrade Project. He solicited bids and purchased fabricated steel for j installation on a 125-ton crane runway girder modification. This work also included field support to construction. O O SA- I
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k] As a civil / mechanical engineer he has performed design and analysis of pressure components, piping systems and structures including field support to construction on a broad variety of projects. This work included the use of SAP - based piping stress codes and STRUDL based structures programs. As a project manager he was responsible for nuclear power plant design modification projects ranging in size from $100K to $6M. His responsibilities included administration, scheduling, cost control, technical direction, and clientinterface. Examples of some of the projects he has managed are: NRC Bulletin 79-14 Program, Turkey Point - Piping and pipe support analysis, design modification and field support to construction for 90 percent of all safety- related systems on both units. As - Built / ISI Drawing Program, Turkey Point - Creation of piping stress isometric and pipe support CAD drawings for all safety - related piping systems on both units. These drawings contained information neccesary for implementation of the utility's Second Ten Year ISI Program. Reactor Gas Vent Modification, Prairie Island - Piping and pipe support analysis, design modification, and field support to construction on Unit # 1 reactor. p
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i MARA LAKIS SENIOR CIVIL / STRUCTURAL ENGINEER EDUCATION: Bachelor of Science Degree in Aeronautical Engineering ) University of Minnesota,1961 I Graduate Level courses in Finite Element Analysis, Earthquake Engineering, Reactor Physics Columbia University,1985 and 1986 EXPERIE.NCE: New York Power Authority 1983 - Present Sr. Civil / Structural Engineer Performed extensive design and analysis of piping systems and supports in I accordance with requirements of ANSI, AISC and regulatory codes. Work performed at Authority's both nuclear and fossil plants. SQUG certified as a Seismic Capability Engineer Responsible for walk-downs and seismic qualification of safety related equipment for the USI A-46 and IPEEE programs at IP3 and JAF Nuclear Power Plants. 1 Represented the Authority at technical meetings with vendors (Westinghouse, l General Electric, and Brown Boveri), reviewing and checking their engmeenng : I calculations. Q (/ Computer programs used: NUPIPE, ANSYS, ADLPIPE, RELAP4/ MOD 5 and STARDYNE ! Member: ERPI Pressure Integrity Subcommittee l Gibbs and Hill, Inc., New York, N.Y. 1979-1983 Applied Mechanics Engineer Performed steamhammer and waterhammer analysis on the Comanche Peak Project, and piping stress analysis due to these events, including support review in accordance with requirements of Section III of the ASME and B & PV Code. Co-authored: " Hydrodynamic and Structural Effects Due to the Feedwater Line Blowdown with Check Valve Slam", ASME Conference, pp.115 PVP, Volume - 84, July 1982. Boeing Company, Seattle, Washington 1961-1966 Research Engineer
. Performed missile flight performance analysis, probability analysis, weapon system integration, flight test performance prediction for various defense systems, l and wird tunnel testing of optimum configurations.
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PRllT OKAS, P.E. NEW YORK POWER AUTHORITY 123 MAIN STREET, WHITE PLAINS, NY 10601 O EXPERIENCE
SUMMARY
l Registered Professional Engineer with over twenty-five years of experience in areas of project management, project engineering, analysis and design of structures and components, equipment qualification, procurement, construction supervision and inspection of nuclear / fossil power plants and ancillary structures. Responsible Engineer for the implementation of diversified projects from inception to completion. Established project objectives; prepared cost estimates, schedules, conceptual designs and assessed the economic benefits of projects for senior management approval through formal presentations. Prepared bid solicitation documents; evaluated proposals; and made recommendations for contract awards. Supervised in-house work, and work of the Architect-Engineer and Constructor. Performed facility irispections and retrofit work. Participated in contract litigations, claim analysis and dispute resolutions. Prepared project reports and appraised senior management of progress. Interacted with vendors, clients, general contractors, and regulators. I EDUCATION: MBA; Finance and Management L Adelphi University, NY,1987 BE; Civil Engineering
' City College of New York,1974 Other: SOUG/EPRI USI A-46; Walkdown Screening and Seismic Evaluation Training Course,1994.
Management Studies; New York University School of Continuing Education,1987
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BWiVOperating Fundamentals Course GE Nuclear Training Services,1986 Dynamics of Structures Course Polytechnic Institute of New York,1976 PROFESSIONAL AFFILIATIONS: Professional Engineer in New York (054843) and in New Jersey (GE22323) (') V EPRl/SOUG Representative for NYPA; EPRI PBI and Piant Materials Subcommittee Member
PRilT OKAS,P.E. EXPERIENCE: i 1984 to New York Power Authority, White Plains, NY l Present Position: Senior Project Engineer; Supervisory Engineer Managing the resolution of USl A-46 for JAFNPP and for IP#3NPP; j using SOUG methodology. Responsible Engineer for implementation j of new facilities at the JAFNPP plant for support and for administrative ! functions. Inspected and upgraded plant structures and equipment
- supports for code compliance. Supervised and reviewed detailed
- engineering, modification packages and construction work. Performed
- equipment qualification and procurement. Interfaced with industry l regulators.
l i j 1975 to Ebasco Services Inc., NYC and Long Island
- 1984 Position: Senior Engineer
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1 Supervised engineering and construction activities from corporate offic'e l' and from sites, for new nuclear power plant design, and for facility retrofit work.' Performed design, review and inspection of steel and i concrete structures. Prepared design and procurement specifications.
] Field liaison from home office for construction related problems. Used computer programs to optimize the design.
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] 1972 to American Electric Power, New York l ] 1975 Position: Structural Design Engineer
- Performed analysis, design and review of structures for the j construction of new power plant facilities. Reviewed the design of a i 1,200 feet tall steel stack liner.
i 1969 to Gibbs and Hill, Inc., New York [ 1972 Position: Associate Design Engineer b *? Performed steel and concrete desigr, work for ? pport of railroad electrification structures. Scope included site insp Jon and structural assessment. 1965 to Ebasco Services, Inc., New York Office ; 1969 Position: Structural Designer Performed structural design, layouts and detailing for the construction of new power plant facilities. Reviewed shop drawings.
, PERSONAL: Date of Birth: September 28,1942 Citizenship: USA
REFERENCES:
Will furnish upon request.
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i ROBERT S. KESTER RD #10, Box 1040, Oswego, NY 13126 (315) 349-6598 RK XPERIEHCE: NEW YORK POWER AUTHORITY SITE ENGINEERING DEPARTMENT JAMES A. FITZPATRICK NUCLEAR POWER PLANT l 1989 - Present PLANT ENGINEER Provides civil / mechanical engineering expertise for plant design modifications and the resolution of operations and maintenance problems. STONE & WEBSTER ENGINEERING CORPORATION NINE MILE POINT NUCLEAR STATION, UNIT 2 1937 - 1989 ASSISTANT LEAD ENGINEER l Supervised personnel performing engineering and design activities pertaining to all piping, duct, and instrumentation supports. Responsibilities included: assessing and responding to client problem reports; approving new designs for constructability and technical i adequacy; maintaining interface with other engineering disciplines, construction, Quality Assurance, and client personnel; and providing manhour estimates and schedule for proposed modifications. 1984 - 1987 TASK ENGINEER ) r m Responsible for providing technical direction to field engineers making 's urgently needed design changes to support mechanical and instrumentation contractors. Developed. construction training classes for fabrication , and erection of piping supports. Also responsible for evaluating ! material inventory and initiating procurement activities as required. 1981 - 1984 FIELD ENGINEER Provided design solutions for structural and mechanical installation problems. STONE & WEBSTER ENGINEERING CORPORATION CHERRY HILL OPERATIONS CENTER - CHERRY HILL, N.J. 1980 - 1981 EN(INffR Gained experience in the Structural Mechanics, Mechanical, Pipe Stress, and Pipe Support disciplines designing the River Bend Nuclear Station. COLORADO GENERAL, INC. 1979 CONSTRUCTION ENGINEER Responsible for construction layout of structures for a transportation facility in Vail, Co.
- Lafayette College - Bachelor of Civil Engineering - 1980
REFERENCES:
References will be furnished upon request.
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n STEPHEN ANAGNOSTIS V Education Massachusetts Institute of Technology, M. S. Structural Engineering,1976 ' Columbia University School of Engineering, B. S. Civil Engineering,1974 Professional History Stevenson & Associates, Boston, Massachusetts, Project Manager 1983 - Present Managed and participated in many consulting projects relating to seismic evaluation of equipment and structures at nuclear power facilities including: A-46 and IPEEE walk downs and analyses, in-situ modal testing of equipment, analysis of raceway systems, analytical investigations of equipment and of structures. Managed and participated in the development of several seismic related software packages used by nuclear power facilities including: GlPPER -implementation and management of GIP-based A-46 projects, EDASP- direct generation of in- . structure response spectra, PCMODAL - generation of dynamic models of ; structures using in-situ modal test data. URS / John A. Blume & Associates, Boston, Massachusetts, Project Engineer, l 1982 - 1983; Senior Engineer, 1980- 1982 Involved in dynamic structural analysis and testing. Had lead technical responsibility for a two year effort to develop a seismic evaluation criteria for raceways at eight of the oldest United States nuclear power stations sponsored by the Systematic Evaluation Program (SEP) Owner's Group. This effort included the design, supervision, and data analysis of full-scale shake table tests, cyclic fatigue tests of raceway components, and development of evaluation techniques incorporating the test results.
.a Chades Stark Draper Laboratory, Cambridge, Massachusetts, Technical Staff, 1976 - 1980; Draper Fellow, 1974-1976 Involved in the assessment of spaced based surveillance and defense systems for the Defense Advanced Research Projects Agency. Helped author a software simulation system to assess the capabilities of spaced based optical systems including structural vibrations, control dynamics, and optical performance.
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O O WALTER DJORDJEVIC SEISMIC EXPERT AND WALKDOWN TEAM MEMBER EDUCATION: B.S. - Civu Engineering, University of Wisconsin at Madison,1974 M.S. - Structural Engineering, Massachusetts institute of Technology,1976 REGISTRATION: State of Califomia, State of Wisconsin, Commonwealth of Massachusetts, State of Michigan PROFESSIONAL HISTORY: Stevenson & Associates, Inc., Vice President and General Manager of the Boston office,1983 - present - URS/ John A. Blume & Associates, Engineers, Boston, Massachusetts, General Manager, 1980 1983; San Francisco, Califomia. Supervisory Engineer, 1979 - 1980 , Impell Corporation, San Francisco, California, Senior Engineer, 1976 1979 Stone & Webster Engineering Corporation, Boston, Massachusetts, Engineer, 1974 - 1976 PROFESSIONAL EXPERIENCE: Mr. Djordjevic founded the Stevenson & Associates Boston office in 1983 and serves as Vice President and General Manager of the Boston area office. Mr. Djordjevic is expert in the area of dynamic qualification of electrical and mechanical equipment. He has par-ticipated in and managed over twenty major projects involving the evaluation and qualification of vibration sensitive equipment and seismic hardening of equipment. As demonstrated by his committee work and publications, Mr. Djordjevio has participated in and contributed steadily to the development of equipment qualification and vibration hardening methodology. Mr. Djordjevic's previous walkdown experience included all of the SEP plants (8 plants), Nine Mile Unit 1, D.C. Cook - Units 1 & 2, the Hanford Reservation Purex facility and the Savannah River Plant Reservation L-Reactor. Representative projects include overseeing the SEP shake-table testing of electrical raceways, in-situ testing of control panels and instruNtntation racks at various nuclear facilities, equipment anchorage walkdowns and eval-untions at various nuclear faculties, principal author of the CERTIVALVE software package to evaluate nuclear service valves, and contributing author in the development of the ANCHOR and EDASP software packages commercially distributed by Stevenson & Associates. Mr. Djordjevic has been involved extensively in the reassessment of safety-related equipment for commercial nuclear facBities and govemment U.S. Department of Encrgy facilities, for which he maintains an active Q-clearance status. He has served on advisory groups and review teams touring older existing nuclear facilities to assess safety and has performed earthquake reconnaissance at such installations following seismic events. O WD-1
W. Djordjevic PROFESSIONAL GROUPS: Member, institute of Electrical and Electronics Engineers, Nuclear Power Engineering Committee Working Group SC 2.5 (IEEE-344) Chairman, American Society of Civil Engineers Nuclear Structures and Materia's Committee, Working Group for the Analysis and Design of Electrical Cable Support Systems Member, American Society of Mechanical Engineers Operation, Application, and Components Committee on Valves, Working Group SC-5 O 1 I O WD 2
ps Appendix B - Screening Verification Data Sheets (SVDS) This appendix contains the SVDS for all Class 0 through Class 20 equipment on the Seismic SSEL. The SVDS are formatted as specified in GIP Section 4.6. Each sheet of the SVDS is signed by the Seismic Capability Engineers (SCEs) who walked down the equipment listed on that sheet. As a result, the equipment is sorted first by the SCEs and then by equipment ID. The SCEs that signed the SVDS are listed below. SVDS Sheet # SCEs 1 Arun Pal, Robert Kester 2 - 11 Arun Pal, Steve Anagnostis 12 -17 Mara Lakis, Walter Djordjevic 18 Priit Okas, Doug Huwe 19 Priit Okas, Robert Kester, Steve Anagnostis 20 - 21 Priit Okas, Mara Lakis, Steve Anagnostis 22 - 24 Priit Okas, Steve Anagnostis ; 25 - 26 Walter Djordjevic, Steve Anagnostis ' In order to help find a particular equipment in the SVDS, the SVDS is foi; owed by a list sorted by : equipment ID that cross references the equipment ID to the SCEs. l b G i l l
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l l l I l O JAFNPP A-46 Seismic Evaluation Report I September 1995 Appendix B
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JAMES A. FITZPATRICK NUCLEAR POWER PLANT Page 1/26 SCREENING VERIFICATION DATA SHEET (SVDS) Eq. Eq. ID Sys/Eq. Desc Bldg. F1 El. Rm or Base El. <40'? Cap. Demd. Cap > Caveats Anctor Interact Equip Cl Rw/Cl Spec. Spec Demd? OK7 OK7 OK7 OK? 8 23MOV-16 HPCI TURBINE STEAM SUPPLY OUTBD ISOL VALVE RB 273.33 2W 272.00 Yes BS GRS Yes Yes N/A Yes Yes (' Certificaton: Certifcation: All the informaton contained on tnis Screening Venfication Data Sheet (SVDS) is, to the best of our The information provided to the Seismic Capabihty Engineers regarding systems and operations of knowledge and belief, correct and accurate. "All information" includes each entry and conclusion the equipment contained in the SVDS is, to the best of our knowledge and belief, correct and (whether venfied to be seismically adequate or not). accurate. Approved: (Senatures of all Seismic Capability Engineers on the Seismic Review Team (SRT) are Approved: (One signature of Systems or Operatens Engineer is required if the Seismic Capabihty required; there should be atleast two on the SRT. All signatories should agree with all the entnes Engineers deem it necessary ) and conclusions. One signatory should be a icensed professional engin .r.) l Arun Pal l l Il b l
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b l I l l Pnnt or Type Name Signature ' Dale Pnnt or Type Name Sgnature Date l Robert Kester l '"[ e2 .f l l l l Pnnt or Type Name Sgn6ture ' Ddte Print or Type Name Signature Date I I I I l i I Pnnt or Type Name Signature Date Pnnt or Type Name Sgnature Date
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- JAMES A. FITZPATRICK NUCLEAR POWER PLANT Page 2/26 SCREENING VERIFICATION DATA SHEET (SVDS)
Eq. Eq ID Sys/Eq. Desc Bldg. FI El Rm or l Base Et <40'? Cap. Demd. Cap > Caveats Anchor Interact Equtp Cl Rw!CI Spec. Spec Demd? OK? OK? OK? OK? 7 03AOV-32 CRD B SDIV TANK B INNER VENT ISOL VALVE RB 272.00 3D 300 00 Yes BS GRS Yes Yes N/A Yes Yes 7 03AOV-33 CRD B SDIV TANK B INNER DRAIN ISOL VALVE RB 272.00 3D 272.00 Yes BS GRS Yes Yes N/A Yes Yes 7 03AOV-34 CRD B SDIV TANK B OUTER VENT ISOL VALVE RB 272.00 3D 300.00 Yes BS GRS Yes Yes N/A Yes Yes 7 03AOV-35 CRD B SDIV TANK B OUTliR DRAIN ISOL VALVE RB 272.00 3D 272.00 Yes BS GRS Yes Yes N/A Yes Yes 7 03AOV-36 CRD A SDIV TANK A tNNE,R VENT 150L VALVE RB 272.00 2P 300 00 Yes BS GRS Yes Yes N/A Yes Yes 7 03AOV-37 CRD A SDIV TANK A INNL9t DRAIN ISOL VALVE RB 272.00 2P 272.00 Yes B3 GRS Yes Yes N/A Yes Yes 7 03AOV-38 CRD A SDIV TANK A GUTER VENT ISOL VALVE RB 272.00 2P 300.00 Yes BS GRS Yes Yes N/A Yes Yes 7 03AOV-39 CRD A SDIV TANK A OUTER DRAIN ISOL VALVE RB 272.00 2P 272 00 Yes BS GRS Yes Yes N/A Yes Yes 20 09-21 NUCLEAR STEAM TEMP RECORD PANEL CR 300 00 9.5.C 300 00 Yes BS GRS Yes Yes Yes Yes Yes 20 09-3 NUCLEAR STATION MAIN CONTROL BOARD CR 300.00 10 F 300 00 Yes BS GRS Yes Yes Yes No No 20 09-32 CHANNEL A RHR/RCIC RELAY PANEL RR 284 67 9 5,F 286 00 Yes BS GRS Yes Yes Yes No No 20 09-33 CHANNEL B RHR/RCIC RELAY PANEL RR 284.67 9.F 286 00 Yes BS GRS Yes Yes Yes Yes Yes 20 09-39 HPCI RELAY PANEL RR 284 67 9.G 286.00 Yes BS GRS Yes Yes Yes Yes Yes 20 09-45 AUTO BLOWDOWN RELAY CABINET RR 284 67 9 5.FG 286.00 Yes BS GRS Yes Yes Yes No No 20 09-46 CORE SPRAY CHANNEL A RELAY CABINET RR 284 67 9.5.FG 286 00 Yes BS GRS Yes Yes Yes No No 20 09-47 CORE SPRAY CHANNEL B RELAY CABINET RR 284 6/ 9.FG 286 00 Yes BS GRS Yes Yes Yes Yes Yes 20 09-5 REACTOR CONTROL MAIN CONTROL BOARD CR 300.00 10.5 E 300 00 Yes BS GRS Yes Yes Yes No No 20 09-6 BALANCE OF PLANT (MECH) MAIN CONTROL BOARD CR 300.00 10 E 300 00 Yes BS GRS Yes Yes Yes No No 20 09-95 EMERGENCY CORE COOLING SYSTEM DIV 1 A/C TRIP CABINET RR 284.67 10.5,G 286.00 Yes BS GRS Yes No Yes Yes No 20 09-96 EMERGENCY CORE COOLING SYSTEM DIV 2 B/D TRIP CABINET RR 284 67 10 5.F 286 00 Yes BS GRS Yes No Yes Yes No 20 09AR-5A (RED) A AUXILIARY RELAY CABINET RR 284 67 10.5. E 286 00 Yes BS GRS Yes Yes Yes Yes Yes 20 09AR-58 (BLUE) B AUXILIARY RELAY CABINET RR 2840/ MS, E 286 00 Yes BS GRS Yes Yes Yes Yes Yes 18 10DPIS-125A RHR LOOP A DIFF PRESS INDIC SWITCH EQ RB 242.00 4. A 242.67 Yes BS GRS Yes Yes Yes Yes Yes 18 10DPIS-1258 RHR B DISCH HDR FLOW DIFF PRESS INDIC SWITCH RB 242.00 3, D 242.67 Yes BS GRS Yes Yes Yes Yes Yes 8 10MOV-25A RHR A LPCI INBD INJ VALVE RB 286 50 3R 286.50 Yes BS GRS Yes Yes N/A Yes Yes 8 10MOV-25B RHR B LPCI INBD INJ VALVE RB 286 50 2T 286.50 Yes BS GRS Yes Yes N/A Yes Yes Certification: Certificatson-All the information contained on this Screening Venficaten Data Sheet (SVDS) is, to the best of our The information provided to the Seismic Capabihty Engineers regarding systems and operatens of knowledge and belief, correct and accurate. "All information" includes each entry and cor'clusion the equipment contained in the SVDS is, to the best of our knowledge and belief, correct and (whether venfied to be seismically adequate or not). accurate. Approved: (Sqnatures of all Seismic Capabihty Engineers on the Seismic Review Team (SRT) are Approved: (One signature of Systems or Operations Engineer is required if the Seismic Capabihty required; there should be atleast two on the SRT. All signatories should agree with all the entnes Engineers deem it necessary.) and conclusions. One signatory should be a hcensed profess' I enginer.) p Arun Pat l ! l l l l l l ._ . - - Pnnt of Type Name Sqnature Date Pnnt or Type Name Sqnature Date
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l Steve Anagnostis l l l l Pnnt or Type Name /
/ Sufriature Date Pnnt or Type Name Sgnature Date i I I I I I l Pnnt or Type Name Sqnature Date Pnnt or Type Name Sgnature Date J
JAMES A. FITZPATRICK NUCLEAR POWER PLANT Page 3/26 SCREENING VERIFICATION DATA SHEET (SVDS) Eq Eq. ID Sys/Eq. Desc Bldg. Fl El. Rm or Base El <40'? Cap. Demd. Cap > Caveats Anchor interact Equip Cl Rw/Cl Spec. Spec Demd? OK7 OK? OK? OK7 8 10MOV-27A RHR A LPCI OUTBD INJ VALVE RB 286.50 3R 286.50 Yes BS GRS Yes Yes N/A Yes Yes 8 10MOV-27B RHR B LPCI OUTBD INJ VALVE RB 286 50 2T 286.50 Yes BS GRS Yes Yes N/A Yes Yes 8 10MOV-89A RHR HEAT EXCH A SERV WATER OUTLET ISOL VALVE RB 272.00 2A 272.00 Yes BS GRS Yes Yes N/A Yes Yes 8 10MOV-898 RHR HEAT EXCH B SERV 41ATER OUTLET ISOL VALVE RB 272.00 2.5 0 272.00 Yes BS GRS Yes Yes N/A Yes Yes 6 10P-1 A RHR SERVICE WATER PUMP A SP 255 00 26 B 255 00 N/A ABS CRS Yes Yes Yes Yes Yes 6 10P-18 RHR SERVICE WATER PLBP B SP 255 00 25 B 255 00 N/A ABS CRS Yes Yes Yes Yes Yes 6 10P-1C RHR SERVICE WATER PUMP C SP 255.00 26.5 B 255 00 N/A ABS CRS Yes Yes Yes Yes Yes 6 10P-1D RHR SERVICE WATER PUMP D SP 255.00 25 8 255 00 N/A ABS CRS Yes Yes Yes Yes Yes ' 7 10RV-43A RHR HEAT EXCHANGER A TUBE SIDE RELIEF VALVE RB 272.00 2.5 A 272.00 Yes BS GRS Yes Yes N/A Yes Yes 7 10RV-43B RHR HEAT EXCHANGER B TUBE SIDE RELIEF VALVE RB 272.00 2.5 D 272.00 Yes BS GRS Yes Yes N/A Yes Yes 7 10RV-46A RHR HEAT EXCHANGE A SHELL SIDE RELIEF VALVE RB 272.00 2.5 A 272.00 Yes BS GRS Yes Yes N/A Yes Yes 7 10RV-468 RHR HEAT EXCHANGER B SHELL SIDE RELIEF VALVE RB 272.00 2.5 D 272.00 Yes BS GRS Yes Yes N/A Yes Yes 8 10SOV-101A RHRSW PUMP A MOTOR COOLING WATER RETURN SOLENOID SP 255.00 26 B 255.00 Yes BS GRS Yes Yes N/A Yes Yes VALVE 10SOV-101B RHRSW PUMP B MOTOR COOLING WATER RETURN SOLENOID SP 255.00 25 B 255.00 Yes BS GRS Yes Yes N/A Yes Yes ! 8 VALVE 8 10SOV-101C RHRSW PUMP C MOTOR COOLING WATER RETURN SOLENOID SP 255.00 26.5 B 255 00 Yes BS GRS Yes Yes N/A Yes Yes VALVE 8 10SOV-101D RHRSW PUMP O MOTOR COOLING WATER RETURN SOLENOID SP 255.00 25 8 255 00 Yes BS GRS Yes Yes N/A Yes Yes VALVE 7 10SV-74A RHR HEAT EXCHANGER A STEAM INLET SAFETY VALVE RB 294.00 2A 300 00 Yes BS GRS Yes Yes N/A Yes Yes 7 10SV-748 RHR HEAT EXCHANGER B STEAM INLET SAFETY VALVE RB 272.00 2D 272.00 Yes BS GRS Yes Yes N/A Yes Yes 18 15PS-122A RBCLC PUMPS DISCH HDR PRESS SWITCH RB 300.00 4. A 300 00 Yes BS GRS Yes Yes Yes Yes Yes 18 15PS-122B RBCLC PUMPS DISCH HDR PRESS SWITCH RB 300 00 4.5, A 300.00 Yes BS GRS Yes Yes Yes Yes Yes 18 15PS-122C RBCLC PUMPS DISCH HOR PRESS SWITCH RB 300.00 4, A 300.00 Yes BS GRS Yes Yes Yes Yes Yes 18 15PS-122D RBCLC PUMPS DISCH HOR PRESS SWITCH RB 300 00 4.5, A 300.00 Yes BS GRS Yes Yes Yes Yes Yes Certification: Certification: All the information contained on this Screening Venfication Data Sheet (SVDS) is, to the best of our The information provided to the Seismic Capability Engineers regarding systems and operations of knowledge and bellef, correct and accurate. "All information" includes each entry and conclusion the equipment contained in the SVDS is, to the best of our knowledge and belief, correct and (whether venfied to be seismically adequate or not). accurate. Approved: (Signatures of all Seismic Capability Engineers on the Seismic Review Team (SRT) are Approved: (One signature of Systems or Operations Engineer is required if the Seismic Capability required; there should be atleast two on the SRT. All signatories sho agree with all the entries Engineers deem it necessary.) and conclusions. One signatory should be a licensed pro ional eng' r.) l Arun Pal l l !l l l l Pnnt or Type Name Sqnature Date Pnnt or Type Name Sgnature Date l Steve Anagnostis l ' @S[hDate' Pnnt or Type Name l Sgnature l Date l Pnnt or Type Name / Grgnature l l l 1 I I I Pnnt or Type Name Sqnature Date Pnnt or Type Name Signature Date
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JAMES A. FITZPATRICK NUCLEAR POWER PLANT Page 4/26 SCREENING VERIFICATION DATA SHEET (SVDS) Eq Eq ID Sys/Eq Desc Bldg. FI El. Rmor Base El <407 Cap. Dernd. Cap > Caveats Anchor Interact Equip Cl Rw/Cl Spec. Spec Dernd? OK? OK7 OK? OK7 19 16-1RTD-131 A TORUS BULK TEMP MONITOR 0 AZIMUTH BAY L X-232 RESIST SU 227.50 4P 227.50 Yes BS GRS Yes Yes N/A Yes Yes TEMP DETECTOR EQ 19 16-1RTD-1318 TORUS BULK TEMP MONITOR 0 AZIMUTH BAY L X-232 RESIST SU 227.50 4P 227.50 Yes BS GRS Yes Yes N/A Yes Yes TEMP DETECTOR EO ,. i 19 16-1RTD-132A TORUS BULK TEMP MONITOR 22.5 AZIMUTH BAY K X-233 RESIST SU 227.50 $P 227.50 Yes BS GRS Yes Yes N/A Yes Yes TEMP DETECTOR EQ .l$ 19 16-1RTD-132B TORUS BULK TEMP MONITOR 22.5 AZlMUTH BAY K X-233 RESIST SU 227.50 5P 227.50 Yes BS GRS Yes Yes N/A Yes Yes TEMP DETECTOR EO 19 16-1RTD-133A TORUS BULK TEMP MONITOR 45 AZIMUTH BAY J X-234 RESIST SU 227.50 6R 227.50 Yes BS GRS Yes Yes N/A Yes Yes TEMP DETECTOR EO 19 16-1RTD-133B TORUS BULK TEMP MONITOR 45 AZIMUTH BAY J X-234 RESIST SU 227.50 6R 227.50 Yes BS GRS Yes Yes N/A Yes Yes TEMP DETECTOR EQ 19 16-1RTD-134A TORUS BULK TEMP MONITOR 67.5 AZIMUTH BAY l X-235 RESIST SU 277.50 6R 227.50 Yes BS GRS Yes Yes N/A Yes Yes THERMAL DETECTOR EQ 19 16-1RTD-134B TORUS BULK TEMP MONITOR 67.5 AZIMUTH BAY l X-235 RESIST SU 277.50 6R 227.50 Yes BS GRS Yes Yes N/A Yes Yes TEMP DETECTOR EQ 19 16-1RTD-135A TORUS BULK TEMP MONITOR 90 AZIMUTH BAY H X-236 RESIST SU 227.50 6T 227.50 Yes BS GRS Yes Yes N/A Yes Yes TEMP DETECTOR EO 19 16-1RTD-1358 TORUS BULK TEMP MONITOR 90 AZIMUTH BAY H X-236 RESIST SU 227.50 6T 227.50 Yes BS GRS Yes Yes N/A Yes Yes TEMP DETECTOR EQ 19 16-1RTD-136A TORUS BULK TEMP MONITOR 112.5 AZlMUTH BAY G X-237 RESIST SU 227.50 6W 227.50 Yes BS GRS Yes Yes N/A Yes Yes TEMP DETECTOR EQ 19 16-1RTD-1368 TORUS BULK TEMP MONITOR 112.5 AZIMUTH BAY G X-237 RESIST SU 227.50 6W 227.50 Yes BS GRS Yes Yes N/A Yes Yes TEMP DETECTOR EQ 19 16-1RTD-137A TORUS BULK TEMP MONITOR 135 AZIMUTH BAY F X-238 RESIST SU 227.50 6W 227.50 Yes BS GRS Yes Yes N/A Yes Yes TEMP DETECTOR EQ Certification: Certification: AM the informahon contained on this Screening Ventication Data Sheet (SVDS)is, to the best of our The information provided to the Seismic Capabshty Engineers regarding systems and operatens of knowledge and belief, correct and accurate. "AH information" includes each entry and conclusion the equipment contained in the SVDS is, to the best of our knowledge and behef, correct and (whether venfied to be seismicaNy adequate or not). accurate. Approved: (Signatures of an Seismic Capabihty Engineers on the Seismic Review Team (SRT) are Approved: (One sgnature of Systems or Operations Engineer is required if the Seismic Capabihty required, there should be atleast two on the SRT. AR signatories shopld agree with au the entnes Engineers deem it necessary.) and conclusions. One signatory should be a hcensed sional enqIneer.) 2 ' II l Arun Pal l _
- l )' l l l l Pnnt or Type Name Signature / Date Pnnt or Type Name Signature Date l WMSh 7 l Steve Anagnostis l l l Pnnt or Type Name / / Ss$ nature Date Pnnt or Type Name Sagnature Date l I l l 1 l l Pnnt or Type Name Signature Date Pnnt or Type Name Sgnature Date
g J U L.) JAMES A. FITZPATRICK NUCLEAR POWER PLANT Page 5/26 SCREENING VERIFICATION DATA SHEET (SVDS) Eq. Eq ID Sys/Eq. Desc { Bldg. F1 El. Rrn or Base El. <40*? Cap. Demd. Cap > Caveats Anchor Interact Equip Spec. Spec Demd? OK7 CI Rw/Cl OK7 OK? OK7 19 16-1RTD-1378 TORUS BULK TEMP MONtTOR 135 AZIMUTH BAY F X-238 RESIST SU 227.50 6W 227.50 Yes BS GRS Yes Yes N/A Yes Yes TEMP DETECTOR EQ 19 16-1RTD-138A TORUS BULK TEMP MONITOR 157.5 AZlMUTH BAY E X-239 RES!ST SU 227.50 5Y 227.50 Yes BS GRS Yes Yes N/A Yes Yes TEMP DETECTOR EQ p 19 16-1RTD-138B TORUS BULK TEMP MONITOR 157.5 AZIMUTH BAY E X-239 RESIST SU 227.50 5Y 227.50 Yes BS GRS Yes Yes N/A Yes Yes TEMP DETECTOR EQ A 19 16-1RTD-139A TORUS BULK TEMP MONITOR 180 AZIMUTH BAY D X-240 RESIST SU 227.50 5Y 227.50 Yes BS GRS Yes Yes N/A Yes Yes TEMP DETECTOR EQ 19 16-1RTD-139B TORUS BULK TEMP MON! TOR 180 AZIMUTH BAY D X-240 RESIST SU 227.50 5Y 227.50 Yes BS GRS Yes Yes N/A Yes Yes TEMP DETECTOR EQ 19 16-1 RTD-140A TORUS BULK TEMP MONITOR 202.5 AZIMUTH BAY C X-241 RESIST SU 227.50 4Y 227.50 Yes BS GRS Yes Yes N/A Yes Yes TEMP DETECTOR EQ 19 16-1RTD-1408 TORUS BULK TEMP MONITOR 202.5 AZlMUTH BAY C X-241 RESIST SU 227.50 4Y 227.50 Yes BS GRS Yes Yes N/A Yes Yes TEMP DETECTOR EQ 19 16-1RTD-141 A TORUS BULK TEMP MONITOR 22.5 AZIMUTH BAY B X-242 RESIST SU 227.50 3W 227.50 Yes BS GRS Yes Yes N/A Yes Yes TEMP DETECTOR EQ 19 16-1RTD-141B TORUS BULK TEMP MONITOR 22.5 AZIMUTH BAY B X-242 RESIST SU 227.50 3W 227.50 Yes BS GRS Yes Yes N/A Yes Yes TEMP DETECTOR EQ 19 16-1RTD-142A TORUS BULK TEMP MONITOR 247.5 AZIMUTH BAY A X-243 RESIST SU 227.50 3W 227.50 Yes BS GRS Yes Yes N/A Yes Yes TEMP DETECTOR EQ 19 16-1RTD-1428 TORUS BULK TEMP MONITOR 247.5 AZIMUTH BAY A X-243 RESIST SU 227.50 3W 227.50 Yes BS GRS Yes Yes N/A Yes Yes TEMP DETECTOR EQ 19 16-1RTD-143A TORUS BULK TEMP MONITOR 270 AZIMUTH BAY P X-244 RESIST SU 227.50 3T 227.50 Yes BS GRS Yes Yes N/A Yes Yes TEMP DETECTOR EQ 19 16-1RTD-1438 TORUS BULK TEMP MONITOR 270 AZIMUTH BAY P X-244 RESIST SU 227.50 3T 227.50 Yes BS GRS Yes Yes N/A Yes Yes TEMP DETECTOR EQ Certification: Certification: All the information contained on this Screening Venfication Data Sheet (SVDS) is, to the best of our The information provided to the Seismic Capability Engineers regarding systems and operations of knowledge and behef, correct and accurate. "All information" includes each entry and condusion the equipment contained in the SVDS is, to the best of our knowledge and belief, correct and (whether venfed to be seismically adequate or not). accurate. Approved: (Signatures of all Seismic Capabihty Engineers on the Seismic Review Team (SRT) are Approved: (One signature of Systems or Operations Engineer is required if the Seismic Capabihty required, there should be atleast two on the SRT. All signatories should agree with all the entries Engineers deem it necessary.) cnd conclusions. One signatory should be a licensed profes ' at enginegr.) l Arun Pal l l lI \ l l l Pnnt or Type Name Signature IDate( ' Pnnt or Type Name Sgnature Date A l Steve Anagnostis 7C l M/h5T l Sqnature l Date l Pnnt or Type Name [ / Segedure
- Date Pnnt or Type Name i I I I I I l Pnnt or Type Name Signature Date Pnnt or Type Name Sqnature Date
( ,~ ( w w JAMES A. FITZPATRICK NUCLEAR POWER PLANT Page 6/26 SCREENING VERIFICATION DATA SHEET (SVDS) Eq. Eq 10 Sys/Eq. Desc Bldg. F1 El. Rm or Base El <40*? Cap. Demd. Cap > Caveats Anchor Interad Equip Cl Rw/Cl Spec. Spec Demd? OK7 OK7 OK7 OK? 19 16-1RTD-144A TORUS BULK TEMP MONITOR 292.5 AZlMUTH BAY O X-245 RESIST SU 227.50 3R 227.50 Yes BS GRS Yes Yes N/A Yes Yes TEMP DETECTOR EO 19 16-1RTD-1448 TORUS BULK TEMP MONITOR 292.5 AZIMUTH BAY O X-245 RESIST SU 227.50 3R 227.50 Yes BS GRS Yes Yes N/A Yes Yes TEMP DETECTOR EO . 19 16-1RTD-145A TORUS BULK TEMP MONITOR 315 AZIMUTH BAY N X-246 RESIST SU 227.50 3R 227.50 Yes BS GRS Yes Yes N/A Yes Yes TEMP DETECTOR EO A 19 16-1RTD-1458 TORUS BULK TEMP MONITOR 315 AZlMUTH BAY N X-246 RESIST SU 227.50 3R 227.50 Yes BS GRS Yes Yes N/A Yes Yes TEMP DETECTOR EO 19 16-1RTD-146A TORUS BULK TEMP MONITOR 337.5 AZIMUTH BAY M X-247 RESIST SU 227.50 4P 227.50 Yes BS GRS Yes Yes N/A Yes Yes TEMP DETECTOR EO 19 16-1RTD-146B TORUS BULK TEMP MONITOR 337.5 AZIMUTH BAY M X-247 RESIST SU 227.50 4P 227.50 Yes BS GRS Yes Yes N/A Yes Yes TEMP DETECTOR EQ 7 23AOV-42 HPCI TURBINE STEAM SUPPLY UPSTR DRAIN ISOL VALVE RB 227.50 1T 227.50 Yes BS GRS Yes Yes N/A Yes Yes 7 23HOV-1 HPCI TURBlNE STOP VALVE RB 227.50 1T 272.00 Yes BS GRS Yes Yes N/A Yes Yes 18 23LT-202A SUPPRESSION POOL HPCI LOGIC LEVEL XMITTER EO RB 227.50 4.5 A 227.50 Yes BS GRS Yes Yes Yes Yes Yes 18 23LT-202B SUPPRESSION POOL HPCI LOGIC LEVEL XMITTER EQ RB 227.50 4.5 D 227.50 Yes BS GRS Yes Yes Yes Yes Yes 8 23MOV-14 HPCI TURBINE STEAM SUPPLY iSOL VALVE RB 227.50 1T 227.50 Yes BS GRS Yes Yes N/A Yes Yes 8 23MOV-17 HPCI BOOSTER PUMP P-1B SUCT FROM 33TK-1 A & B ISOL VALVE RB 242.67 3A 242.67 Yes BS GRS Yes Yes N/A Yes Yes 8 23MOV-24 HPCI FULL FLOW TEST RETURN TO CST 33TK-1A & B DNSTR ISOL RB 262.42 3P 227.50 Yes BS GRS Yes Yes N/A Yes Yes VALVE 8 23MOV-57 HPCI BOOSTER PUMP P-1B SUCT FROM SUPPRESSION POOL RB 227.50 1R 227.50 Yes BS GRS Yes Yes N/A Yes Yes DNSTR ISOL VALVE 6 23P-150 HPCI TURBINE AUX LUBE OIL PUMP RB 227.50 1T 227.50 Yes BS GRS Yes Yes Yes Yes Yes 5 23P-1M HPCI MA!N PUMP RB 227.50 1T 227.50 Yes BS GRS Yes Yes Yes Yes Yes 7 23RV-106 HPCI AUX Olt PUMP P-150 DISCH RELIEF VALVE RB 227.50 1T 272.00 Yes BS GRS Yes Yes N/A Yes Yes 7 23RV-107 HPCI MAIN LUBE OIL PUMP P-1MO DISCH RELIEF VALVE RB 227.50 1T 272 00 Yes BS GRS Yes Yes N/A Yes Yes 7 23SV-34 HPCI BOOSTER PUMP P-1B SUCT SAFETY VALVE RB 227.50 1R 227.50 Yes BS GRS Yes Yes N/A Yes Yes Certification: Certification: All the informatsn contained on this Screening Venfication Data Sheet (SVDS) is, to the best of our The information provided to the Seismic Capabihty Engineers regarding systems and operations of knowledge and behef, correct and accurate. "All information" includes each entry and conclusion the equipment contained in the SVDS is, to the best of our knowledge and belief, correct and (whether venfied to be seismically adequate or not). accurate. Approved:(Signatures of all Seismic Capabihty Engineers on the Seismic Review Team (SRT) are Approved (One sgnature of Systems or Operations Engineer is required sf the Seismic Capabihty required, there should be atleast two on the SRT. All signatories sh >uld agree wh all the entries Engineers deem it necessary.) cnd conclusions. One signatory should be a licensed p sional enlineer.) Arun Pal l x l I l l l l Pnnt or Type Name Sgnature 'Datel Pnnt or Type Name Sgnature Date l Steve Anagnostis l W)7[dI' Pnnt or Type Name l Sqnature l Date l Pnnt or Type Name [f 4!Rjnature ' Dath I I I I l l l Pnnt or Type Name Sgnature Date Pnnt or Type Name Sgnature Date
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- JAMES A. FITZPATRICK NUCLEAR POWER PLANT Page 7/26 SCREENING VERIFICATION DATA SHEET (SVDS)
Eq. Eq.ID Sys/Eq. Desc Bidg. Fi EL Rmor Base El <40'? Cap. Demd. Cap > Caveats Anchor interact Equip CI Rw'Cl Spec. Spec Demd? OK? OK7 OK7 OK7 7 23SV-66 HPCI BOOSTER PUMP P-1B RECIRC SAFETY VALVE RB 227.50 1R 227.50 Yes BS GRS Yes Yes N/A Yes Yes 5 23TU-2 HPCI PUMP DRIVE TURBINE RB 227.50 1T 227.50 Yes BS GRS Yes Yes Yes Yes Yes 20 27 CAD CONTAINMENT AIR DtLUTION PANEL RR 284.67 9. E 286.00 Yes BS GRS Yes No Yes Yes No 20 27 MAP MONITORING ANALYSIS P/LNEL RR 284 67 10 E 286.00 Yes BS GRS Yes Yes Yes Yes Yes 18 27PCV-116A 27FCV-103A SIGNAL CONpRTER NITROGEN SUPPLY PRESS RB 272.00 2T 272.00 Yes BS GRS Yes Yes Yes Yes Yes REGULATOR .lW 18 27PCV-1168 27FCV-1038 SIGNAL CONVERTER NITROGEN SUPPLY PRESS RB 272.00 2T 272.00 Yes BS GRS Yes Yes Yes Yes Yes REGULATOR 18 27PT-115A2 DRYWELL DIV I WIDE RANGE PRESS XMITTER EQ RB 344.50 6W 326 00 N/A ABS CRS Yes Yes Yes Yes Yes 18 27PT-11582 ORYWELL DIV 11 WIDE RANGE PRESS XMITTER EQ RB 344.50 6W 326 00 N/A ABS CRS Yes Yes Yes Yes Yes 8 46MOV-101 A EMERGENCY SERVICE WATER LOOP A SUPPLY HEADER ISOL SP 255.00 26 B 255.00 Yes BS GRS Yes Yes N/A Yes Yes VALVE 8 46MOV-101B EMERGENCY SERVICE WATER LOOP B SUPPLY HEADER ISOL GP 255.00 2d B 255.00 Yes BS GRS Yes Yes N/A Yes Yes VALVE 8 46MOV-102A EMERGENCY SERVICE WATER PUMP A TEST VALVE SP 255 00 26 B 255.00 Yes BS GRS Yes Yes N/A Yes Yes 8 46MOV-102B EMERGENCY SERVICE WATER PUMP B TEST VALVE SP 255.00 25 B 255.00 Yes BS GRS Yes Yes N/A Yes Yes 6 46P-2A EMERGENCY SERVICE WATER PUMP A SP 255 CO 26 B 255 00 N/A ' ABS CRS Yes Yes Yes Yes Yes 6 46P-2B EMERGENCY SERVICE WATER PUMP B SP 255.00 25 B 255 00 N/A ABS CRS Yes Yes Yes Yes Yes 14 71ACA4 DISTRIBUTION PANEL 71ACA4 EMERGENCY CONTROL & INST EG 272.00 24 A 272.00 Yes BS GRS Yes Yes Yes Yes Yes POWER A 14 71ACB2 DISTRIBUTION PANEL 71 ACB2 EMERG CONTROL & INST POWER B RR 284 67 12 E 286.00 Yes BS GRS Yes Yes Yes Yes Yes 14 71ACB4 DISTRIBUTION PANEL 71ACB4 EMERGENCY CONTROL & INST EG 272.00 25 A 272.00 Yes BS GRS Yes Yes Yes Yes Yes POWERB 1 71BMCC-1 RB WEST CRESCENT DC MOTOR CONTROL CENTER RB 242.67 1R 242.67 N/A ABS CRS No No Yes Yes No 1 71BMCC-2 RB EAST CRESCENT DC MOTOR CONTROL CENTER RB 242.67 1D 242.67 N/A ABS CRS No No Yes Yes No 1 71BMCC-3 RB WEST CRESCENT DC MOTOR CONTROL CENTER RB 242.67 1R 242.67 N/A ABS CRS No No Yes Yes No 1 71BMCC-4 RB EAST CRESCENT DC MOTOR CONTROL CENTER RB 242.67 1D 242.67 N/A ABS CRS No No Yes Yes No Certification: Certification: All the information contained on this Screening Verificaten Data Sheet (SVDS) is, to the best of our The information provided to the Seismic Capabihty Engineers regarding systems and operations of knowledge and belief, correct and accurate. "All information" includes each entry and conclusion the equipment contained in the SVDS is, to the best of our knowledge and behef, correct and (whether venfied to be seismically adequate or not). accurate. Approved: (Signatures of all Seismic Capabihty Engineers on the Seismic Review Team (SRT) are Approved: (One signature of Systems or Operations Engineer is required if :he Seismic Capabihty required; there should be atleast two on the SRT. All signatories should agree wi'A a?! the entries Engineers deem it necessary.) tnd conclusions. One signatory should be a hcensed profes nal entneer.) l Arun Pal l . l II l l l Pnnt or Type Name Sgnature i Dat'e Pnnt or Type Name Sgnature Date l Steve Anagnostas l ThT
~ Datd Pnnt or Type Name l
Sqnature l Date l t Pnnt or Type Name [/ Swifiature i I I I I I l Pnnt or Type Name Sqnature Date Pnnt or Type Name Sgnature Date
(p) p U (V) fV) JAMES A. FITZPATRICK NUCLEAR POWER PLANT Page 8/26 SCREENING VERIFICATION DATA SHEET (SVDS) Eq Eq. ID Sys/Eq. Desc Bldg. FI El. Rm or Base El <40"? Cap. Demd Cap > Caveats Anchor Interact Equip CI Rw/Cl Spec. Spec Demd? OK? OK? OK7 OK? 1 71BMCC-6 RB DC MOTOR CONTROL CENTER RB 272.00 8Y 272.00 N/A ABS CRS No Yes Yes No No 14 71DC-A2 DISTRIBUTION PANEL 71DC-A2 DC CONTROL POWER A RR 284.67 10 F 286 00 Yes BS GRS Yes Yes Yes Yes Yes 14 71DC-A4 DISTRIBUTION PANEL 71DC-A4 DC CONTROL POWER A EG 272.00 25 A 272.00 Yes BS GRS Yes Yes Yes Yes Yes 14 71DC-A5 DISTRIBUTION PANEL 71QC-A5 DC CONTROL POWER A RR 284.67 10 G 286.00 Yes BS GRS Yes Yes Yes Yes Yes 14 71DC-B2 DISTRIBUTION PANEL 71QC-82 DC CONTROL POWER B RR 284.67 9F 286.00 Yes BS GRS Yes Yes Yes Yes Yes 3 71DSC-11561 L15 UNIT SUBSTATION TJRNSF T-13 HIGH SIDE DISC SW RB 300 00 2R 300 00 Yes BS GRS Yes Yes Yes Yes Yes 3 71DSC-12561 L25 UNIT SUBSTATION TRANSF T-15 HIGH SIDE DISC SWITCH EB 272.00 18.5 B 272.00 Yes BS GRS Yes Yes Yes Yes Yes 14 71 ESSA 1 SAFEGUARD CONTROL & INST POWER A DISTRIBUTION PANEL RR 284 67 11 C 286.00 Yes BS GRS Yes Yes Yes Yes Yes 14 71ESSB1 SAFEGUARD CONTROL & INST POWER B DISTRIBUTION PANEL RR 284.67 12 E 286.00 Yes BS GRS Yes Yes Yes Yes Yes 3 71H05 4160V SWITCHGEAR DISTRIBUTION (BUS 10500) EG 272.00 24 A1 272.00 N/A ABS CRS Yes Yes Yes Yes Yes 16 711NV-3A LPCI MOV INDEP POWER SUPPLY A INVERTER RB 344.50 5.5 P 344 00 N/A ABS CRS Yes Yes Yes Yes Yes 16 711NV-38 LPCI MOV INDEP POWER SUPPLY B INVERTER RB 344 50 2W 344 00 N/A ABS CRS Yes Yes No Yes No 2 71L15 600V SWITCHGEAR DISTRIBUTION (BUS 11500) RB 300 00 2R 300.00 Yes BS GRS Yes Yes Yes Yes Yes 2 71L16 600V SWITCHGEAR DISTRIBUTION (BUS 11600) RB 300 00 6P 300.00 Yes BS GRS Yes Yes Yes Yes Yes 2 71L25 600V SWITCHGEAR DISTRIBUTION (BUS 12500) EB 272.00 18.5 A1 272.00 Yes BS GRS Yes No No Yes No 2 71L26 600V SWITCHGEAR DISTRIBUTION (BUS 12600) EB 272 00 18.5 B 272.00 Yes BS GRS Yes Yes Yes Yes Yes 1 71MCC-151 600V MOTOR CONTROL CENTER (BUS 115100) RB 272.00 1T 272.00 N/A ABS CRS No No Yes Yes No 1 71MCC-152 600V MOTOR CONTROL CENTER (BUS 115200) RB 272.00 8P 272.00 N/A ABS CRS No No Yes Yes No 1 71MCC-153 600V MOTOR CONTROL CENTER (BUS 115300) RB 242.67 .5 A 242.67 N/A ABS CRS No No Yes No No 1 71MCC-155 600V MOTOR CONTROL CENTER (BUS 115500) RB 242.6' .5 A 242.67 N/A ABS CRS No No Yes Yes No 1 71MCC-156 600V MOTOR CONTROL CENTER (BUS 115600) RB 344.50 3.5 T 344.00 N/A ABS CRS Yes Yes Yes Yes Yes 1 71MCC-161 600V MOTOR CONTROL CENTER (BUS 116100) RB 272.00 1.5 W 272.00 N/A ABS CRS No No No No No 1 71MCC-162 600V MOTOR CONTROL CENTER (BUS 116200) RB 272.00 7D 272.00 N/A ABS CRS No No Yes Yes No 1 71MCC-163 600V MOTOR CONTROL CENTER (BUS 116300) RB 242.67 1.5 D 272.00 N/A ABS CRS No No Yes Yes No 1 71MCC-165 600V MOTOR CONTROL CENTER (BUS 116500) RB 242.67 1.5 D 272.00 N/A ABS CRS No No Yes Yes No 1 71MCC-166 600V MOTOR CONTROL CENTER (BUS 115600) RB 344.50 20 344.00 N/A ABS CRS Yes Yes Yes Yes Yes Cartificatiom Certification: All the information contained on this Screening Venfication Data Sheet (SVDS) is, to the best of our The information provided to the Seismic Capabihty Engineers regarding systems and operations of knowledge and belief, correct and accurate. "All information" includes each entry and conclusion the equipment contained in the SVDS is, to the best of our knowledge and behef, correct and (whether venfied to be seismically adequate or not). accurate. Approved. (Sgnatures of all Seismic Capabihty Engineers on the Seismic Review Team (SRT) are Approved: (One signature of Systems or Operations Engineer is requi.ed if the Seismic Capabihty required; there should be atleast two on the SRT. AB signatones sho Id agree with all the entries Engineers deem it necessary.) and conclusions. One sgnatory should be a licensed professi alengi teer.)
' I l Arun Pal l l l l l l Pnnt or Type Name Sgnature ' Date Pnnt or Type Name Sqnatuie Date l Steve Anagnostis lT Sk Pnnt or Type Name l
Sqnature l Date l Pnnt or Type Name f/ Sitfnature ' Dati i I I I I I l Pnnt or Type Name Sgnature Date Pnnt or Type Name Sqnature Date
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N V h (v h Nv] JAMES A, FITZPATRICK NUCLEAR POWER PLANT Page 9/26 SCREENING VERIFICATION DATA SHEET (SVDS) Eq Eq. ID Sys/Eq. Desc Bldg. FI El. Rm or Base Et <40*? Cap. Demd. Cap > Caveats Anchor interact Equip Cl Rw/Cl Spec. Spec Demd? OK? OK7 OK7 OK? 1 71MCC-251 600V MOTOR CONTROL CENTER (BUS 125100) EB 272.00 18 A 272.00 N/A ABS CRS Yes No Yes Yes No 1 71MCC-252 600V MOTOR CONTROL CENTER (BUS 125200) EB 272 00 18 A 272.00 N/A ABS CRS No No Yes Yes No 1 71MCC-254 600V MOTOR CONTROL CENTER (BUS 125400) EG 272.00 23 A1 272.00 N/A ABS CRS No No Yes Yes No 1 71MCC-261 600V MOTOR CONTROL CF;NTER (BUS 126100) EB 272.00 18 8 272 00 N/A ABS CRS No No Yes Yes No 1 71MCC-262 600V MOTOR CONTROL CENTER (BUS 126200) EB 272.00 18 B 272 00 N/A ABS CRS No No Yes Yes No 1 71MCC-263 600V MOTOR CONTROL CENTER (BUS 126300) AD 300 00 9C 300 00 N/A ABS CRS Yes No Yes Yes No 1 71MCC-264 600V MOTOR CONTROL CENTER (BUS 126400) EG 272.00 25.5 A1 272.00 N/A ABS CRS Yes No Yes Yes No 4 71PT-71 ACA2 EMERGENCY DISTRIBUTION 15KVA TRANSFORMER 71MCC-253- CS 272.00 11 C 272.00 Yes BS GRS Yes Yes Yes Yes Yes OD3 4 71PT-71 ACA4 EMERGENCY DISTRIBUTION 7.5KVA TRANSFORMER 71MCC-254- EG 272.00 24 A 272.00 Yes BS GRS Yes Yes Yes Yes Yes A3A 4 71PT-71 ACB2 EMERGENCY DISTRIBUTION 15KVA TRANSFORMER 71MCC-263- CS 272.00 12 E 272.00 Yes BS GRS Yes Yes Yes Yes Yes OE3 4 71PT-71 ACB4 EMERGENCY DISTRIBUTION 7.5KVA TRANSFORMER 71MCC-264- EG 272.00 26 A 272.00 Yes BS GRS Yes Yes Yes Yes Yes A3A 4 71PT-71 ESSA 1 SAFEGUARD BUS A DISTRIBUTION 15KVA TRANSFORMER 71MCC- CS 272.00 11 C 272.00 Yes BS GRS Yes Yes Yes Yes Yes 252-OC2 4 71 T-13 600V UNIT SUBSTATION L15 TRANSFORMER RB 300 00 2R 300.00 Yes BS GRS Yes Yes Yes Yes Yes 4 71T-16 SWITCHGEAR L26100KVA TRANSFORMER 71-10660 EB 272.00 18 5 AB 272.00 Yes BS GRS Yes Yes Yes Yes Yes 10 73FD-1/ ESW/RHRSW PUMP ROOM A FIRE DAMPER SP 255 00 24.5 BA 255 00 N/A ABS CRS Yes Yes Yes Yes Yes 10 73FD-1B ESW/RHRSW PUMP ROOM B FIRE DAMPER SP 255 00 25.5 BA 255 00 N/A ABS CRS Yes Yes Yes Yes Yes 10 73FD-1C ESW/RHRSW PUMP ROOM B FIRE DAMPER SP 255 00 26 BA 255.00 N/A ABS CRS Yes Yes Yes Yes Yes 10 73FD-1D WEST DIESEL FIRE PUMP ROOM FIRE DAMPER SP 255.00 26.5 BA 255 00 N/A ABS CRS Yes Yes Yes Yes Yes 9 73FN-3A ESW/RHRSW PUMP ROOM EXHAUST FAN A SW 255.00 26 A 255 00 Yes BS GRS Yes Yes Yes Yes Yes 9 73FN-3P ESW/RHRSW PUMP ROOM EXHAUST FAN G SW 255 00 25 A 255 00 Yes BS GRS Yes Yes Yes Yes Yes 10 92FD-1 EMERG DIESEL GEN VENT SUPPLY FANS A & C FRESH AIR SUCT EG 272.00 23 A1 300 00 N/A ABS CRS Yes Yes Yes Yes Yes FIRE DAMPER Certification: Certification: All the information contained on this Screening Venfication Data Sheet (SVDS)is, to the best of our The informahon provided to the Seismic Capabihty Engineers regarding systems and operations of knowledge and behef, correct and accurate. "All information" includes each entry and conclusion the equipment contained in the SVDS is, to the best of our knowledge and behef, correct and (whether venfied to be seismically adequate or not). accurate. Approved: (Sgnatures of all Seismic Capabihty Engineers on the Seismic Review Team (SRT) are Approved: (One senature of Systems or Operations Engineer is required if the Seismic Capability required, there should be atieast two on the SRT. All sgnatories shoqld agree with all the entries Engineers deem it necessary.) and conclusions. One signatory should be a hcensed profes nalengneer.) I b l Arun Pal l - l ll Ml l l l Pnnt or Type Name Sgnature date / Pnnt or Type Name Sgnature Date l Steve Anagnostas 7
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l / Dats Yhhd l Sqnature l Date l Pnnt or Type Name [ / Sfgfiature Pnnt or Type Name l I I I I I l Pnnt or Type Name Sqnature Date Pnnt or Type Name Sqnature Date
I l
,r JAMES A. FITZPATRICK NUCLEAR POWER PLANT Page 10/26 SCREENING VERIFICATION DATA SHEET (SVDS)
Bk1g. FI El. Rm or Base El. <40*? Cap. Demd Cap > Caveats Anchor Interact Equip Eq Eq ID Sys/Eq Desc Rw/Cl Spec. Spec Demd? OK7 OK7 OK7 OK? Cl EG 272.00 23.5 At 300.00 N/A ABS CRS Yes Yes Yes Yes Yes 10 92FD-2 EMERG DIESEL GEN VENT SUPPLY FAN A RECIRC SUCT FIRE DAMPER Yes Yes EG 272.00 24.5 A1 300.00 N/A ABS CRS Yes Yes Yes 10 92FD-3 EMERG DIESEL GEN VENT SUPPLY FAN A DISCH FIRE DAMPER EG 272.00 24.5 A1 300.00 N/A ABS CRS Yes Yes Yes Yes Yes 10 92FD-4 EMERG DIESEL GEN VENj 6UPPLY FAN C RECIRC SUCT FIRE DAMPER Yes Yes EG 272 00 25.5 A1 300 00 N/A ABS CRS Yes Yes Yes 10 92FD-5 EMERG DIESEL GEN VEf4 SUPPLY FAN C DISCH FIRE DAMPER EG 272.00 24 A4 300 00 N/A ABS CRS Yes Yes Yes Yes Yes 10 92 MOD 143A EMERG DIESEL GEN A VENT EXHAUST ISOL DAMPER EG 272.00 25 A4 300 00 N/A ABS CRS Yes Yes Yes Yes Yes 10 92 MOD-143C EMERG DIESEL GEN C VENT EXHAUST ISOL DAMPER EG 272.00 24 A1 300.00 N/A ABS CRS Yes Yes Yes Yes Yes 10 92 MOD-148A EMERG DIESEL GEN VENT SUPPLY FAN A RECtRC SUCT ISOL DAMPER EG 272.00 24.5 At 300 00 N/A ABS CRS Yes Yes Yes Yes Yes 10 92 MOD-14BC EMERG DIESEL GEN VENT SUPPLY FAN C RECIRC SUCT ISOL DAMPER EG 272.00 24 A1 300 00 N/A ABS CRS Yes Yes Yes Yes Yes 10 92 MOD-149A EMERG DIESEL GEN VENT SUPPLY FAN A FRESH AIR SUCT ISOL DAMPER EG 272.00 24.5 A1 300.00 N/A ABS CRS Yes Yes Yes Yes Yes 10 92 MOD-149C EMERG DIESEL GEN VENT SUPPLY FAN C FRESH AIR SUCT ISOL DAMPER EG 272.00 23 A2 300.00 N/A ABS CRS Yes Yes Yes Yes Yes 10 92 MOD-150A EMERG DIESEL GEN VENT SUPPLY FANS A & C FRESH AIR WEST SUPPLY ISOL DAMPER EG 272.00 23 A2 300.00 N/A ABS CRS Yes Yes Yes Yes Yes 10 92 MOD-150C EMERG DIESEL GEN VENT SUPPLY FANS A & C FRESH AIR EAST SUPPLY ISOL DAMPER EG 272.00 24 5 A 272.00 Yes BS GRS Yes Yes Yes Yes Yes 20 93AURP-01 EDG A & C AUX UNDERVOLTAGE RELAY PANEL EG 272.00 24 A3 272.00 Yes BS GRS Yes Yes Yes Yes Yes 20 93ECP-A EDG A ENGINE CONTROL. PANEL EG 272.00 25 A3 272.00 Yes BS GRS Yes Yes Yes Yes Yes 20 93ECP-C EDG C ENGINE CONTROL PANEL EG 272.00 24.A3 272.00 Yes BS GRS Yes Yes Yes Yes Yes 20 93ECSP-A EDG A ENGINE CONTROL SUB PANEL EG 272.00 25.A3 272.00 Yes BS GRS Yes Yes Yes Yes Yes 20 93ECSP-C EDG C ENGINE CONTROL SUB PANEL EG 272.00 24 A2 272.00 Yes BS GRS Yes Yes Yes Yes Yes 17 93EDG-A EMERGENCY DIESEL GENERATOR A EG 272.00 25 A2 272.00 Yes BS GRS Yes Yes Yes Yes Yes 17 93EDG-C EMERGENCY DIESEL GENERATOR C Certification: Certification: All the information contained on this Screening Venfication Data Sheet (SVDS) is, to the best of our The information provided to the Seismic Capabihty Engineers regarding systems and operations of knowledge and behef, correct and accurate. "All information" includes each entry and conclusion the equipment contained in the SVDS is, to the best of our knowledge and behef, correct and (whether venfied to be seismically adequate or not). accurate. Approved: (Signatures of all Seismic Capabihty Engineers on the Seismic Review Team (SRT) are Approved: (One signature of Systems or Operations Engineer is required if the Seismic Capabihty required; there should be atleast two on the SRT. All signatones should agree with all the entries Engineers deem it necessary.) and conclusions. One signatory should be a licensed profe 'onalen ineer.) Arun Pal l , l l l l l l l Pnnt or Type Name Signature ~ Date Pnnt or Type Name Sgnature Date l Steve Anagnostis l Jhb Pnnt or Type Name l Sgnature l Date l Pnnt or Type Name f / Sigtfature / Ddte l I I I I I I Pnnt or Type Name Sgnature Date Pnnt or Type Name Sqnature Date
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J [v] s JAMES A. FITZPATRICK NUCLEAR POWER PLANT Page 11/26 SCREENING VERIFICATlON DATA SHEET (SVDS) Eq. Eq. ID Sys/Eq. Desc Bldg. FI El. Rm or Base El. <40*? Cap. Demd. Cap > Caveats Anchor Interact Equip Cl Rw/Cl Spec. Spec Demd? OK7 OK? OK7 OK7 i 93EGP-A EDG A GENERATOR CONTROL PANEL EG 272.00 24.A1 272.00 Yes BS GRS Yes Yes Yes Yes Yes ; 20 EDG B GENERATOR CONTROL PANEL EG 272.00 25,A1 272.00 Yes BS GRS Yes Yes Yes Yes Yes 20 93EGP-C 93FPAC EDG A & C FORCED PARALLELING PANEL EG 272.00 24.5 A 272.00 Yes BS GRS Yes Yes Yes Yes Yes 20 93P1-A1 EG 272.00 24 A4 272.00 Yes BS GRS Yes Yes Yes Yes Yes 5 EMERGENCY DIESEL GENfRATOR A FUEL OIL TRANSFER PUMP At 93P1-A2 EMERGENCY DIESEL GFJERATOR A FUEL OIL TRANSFER PUMP EG 272.00 24 A4 272.00 Yes BS GRS Yes Yes Yes Yes Yes 5 A2 93P1-C1 EMERGENCY DIESEL GENERATOR C FUEL OIL TRANSFER PUMP EG 272.00 24.5 A4 272.00 Yes BS GRS Yes Yes Yes Yes Yes 5 C1 6 93P1-C2 EMERGENCY DIESEL GENERATOR C FUEL OIL TRANSFER PUMP EG 272.00 24.5 A4 272.00 Yes BS GRS Yes Yes Yes Yes YE C2 Certification: Certification: All the information contained on this Screening Venfication Data Sheet (SVDS) is, to the best of our The information prowded to the Seismic Capabihty Engineers regarding systems and operations of knowledge and behef correct and accurate. "All information" includes each entry and conclusion the equipment contained in the SVDS is, to the best of our knowledge and belief, correct and (whether venfied to be seismically adequate or not). accurate. Approved: (Signatures of all Seismic Capabihty Engineers on the Seismic Review Team (SRT) are Approved: (One signature of Systems or Operations Engineer is required sf the Seismic Capabil.ty required, there should be atleast two on the SRT. All signatories sh Suld agree with all the entries Engineers deem it necessary.) gnd conclusions. One signatory should be a hcensed pro sional en li neer.) l Arun Pat l
% - // l l l l Pnnt or Type Name Signature f D6te Pnnt or Type Name Sgnature Date .
l Steve Anagnostis l NMk Pnnt or Type Name l Signature l Date l Pnnt or Type Name f ,/ S.gadture / Dath l l l l l l 1 Pnnt or Type Name Sgnature Date Pnnt or Type Name Signature Date
.] YI 0
- JAMES A. FITZPATRICK NUCLEAR POWER PLANT Page 12/26 SCREENING VERIFICATION DATA SHEET (SVDS)
Eq. Eq. ID Sys/Eq. Desc Bksg. Fi El. Rm or Base El. <40'? Cap. Demd. Cap > Caveats Anchor Interad Equip Cl Rw/Cl Spec. Spec Demd? OK? OK7 OK7 OK? RB 272.00 5Y 272.00 Yes BS GRS Yes Yes N/A No No 7 03AOV-126(HCU- HCU INLET SCRAM AIR OPER VALVE 02-19) 7 03AOV-127(HCU- HCU OUTLET SCRAM AIR OPER VALVE RB 272.00 $Y 272.00 Yes BS GRS Yes Yes N/A No No 02-19) ,i 8 03SOV-117(HCU- HCU-02-19 SCRAM PILOT AIR SOLENOID OPER VALVE RB 272.00 5Y 272.00 Yes BS GRS Yes Yes N/A Yes Yes 02-19) A N/A Yes Yes RB 272.00 5Y 272.00 Yes BS GRS Yes Yes 8 03SOV-118(HCU- HCU-02-19 SCRAM PILOT AIR SOLENOID OPER VALVE 02-19) 8 03SOV-140A HYDRAULIC CONTROL UNITS BACKUP SCRAM PILOT SOLENOID RB 272.00 3.5 A 272.00 Yes BS GRS Yes Yes N/A Yes Yes VLV EQ 8 03SOV-1408 HYDRAULIC CONTROL UNITS BACKUP SCRAM PILOT SOLENOID RB 272.00 3.5 A 272.00 Yes BS GRS Yes Yes N/A Yes Yes VLV EQ 8 03SOV-31A SDIV A AOV INSTRUMENT AIR SUPPLY SOLENOID VALVE EQ RB 272.00 3.5 A 272 00 Yes BS GRS Yes Yes N/A Yes Yes 8 03SOV-31 B SDIV B AOV INSTRUMENT AIR SUPPLY SOLENOlO VALVE B EO RB 272.00 3.5 A 272.00 Yes BS GRS Yes Yes N/A Yes Yes RB 272.00 5Y 272.00 N/A DOC RRS No Yes Yes No No 0 03TK-125(HCU- WATER ACCUMULATOR 02-19) RB 272.00 5Y 272.00 N/A ' DOC RRS No Yes Yes No No 0 03TK-128(HCU- NITROGEN ACCUMULATOR 02-19) 18 10FT-109B RHR B DISCH HDR FLOW XMITTER RB 227.50 1W 227.50 Yes BS GRS Yes Yes Yes Yes Yes 8 10MOV-15A RHR PUMP A SUCT SHUTDOWN COOLING ISOL VALVE RB 227.50 2A 242.67 Yes BS GRS Yes Yes N/A Yes Yes 8 10MOV-158 RHR PUMP B SUCT SHUTDOWN COOLING ISOL VALVE RB 227.50 20 242.67 Yes BS GRS Yes Yes N/A Yes Yes 8 10MOV-15C RHR PUMP C SUCT SHUTDOWN COOLING ISOL VALVE RB 227.50 3.5 A 242 67 Yes BS GRS Yes Yes N/A Yes Yes 8 10MOV-150 RHR PUMP D SUCT SHUTDOWN COOLING ISOL VALVE RB 227 50 3D 242.67 Yes BS GRS Yes Yes N/A Yes Yes 8 10MOV-16A RHR A MIN FLOW ISOL VALVE RB 242.67 2A 242.67 Yes BS GRS Yes Yes N/A Yes Yes 10MOV-168 RHR B MIN FLOW ISOL VALVE RB 242.67 3D 242.67 Yes BS GRS Yes Yes N/A Yes Yes 8 8 10MOV-34A RHR A TORUS COOLING SUPPLY VALVE RB 242.67 3A 242.67 Yes BS GRS Yes Yes N/A Yes Yes 8 10MOV-348 RHR B TORUS COOLING SUPPLY VALVE RB 242.67 3D 242.67 Yes BS GRS Yes Yes N/A Yes Yes Certification: Certification: All the information contained on this Screening Verification Data Sheet (SVDS) is, to the best of our The information provided to the Seismic Capability Engineers regarding systems and operations of knowledge and belief, correct and accurate. "All information" includes each entry and conclusion the equipment contained in the SVDS is, to the best of our knowledge and beief, correct and (whether venfied to be seismically adequate or not). accurate. Approved. (Signatures of all Seismic Capabihty Engineers on the Seismic Review Team (SRT) are Approved: (One signature of Systems or Operations Engineer is required if the Seismic Capability required; there should be atleast two on the SRT. All signatores should agree with all the entries Engineers deem it necessary.) and conclusions. One signatory should be a licensed professional engineer.) l Mara Lakis l j!4/4 do l 0 l l l l Pnnt or Type Name Sqn ure Date Pnnt or Type Name Sgnature Date Walter Djordjevic l / l l l l l Pnnt or Type Name "" Sqnatur # Datd Pnnt or Type Name Sqnature Date l l l I l I I Pnnt or Type Name Date Pnnt or Type Name Signature Date Sgnatjre
( [ [ (v! ( v V' JAMES A. FITZPATRICK NUCLEAR POWER PLANT Page 13/26 SCREENING VERIFICATION DATA SHEET (SVDS) Sys/Eq. Desc Bldg. FI El. Rm or Base El. <40'? Cap. Demd. Cap > Caveats Anchor Interact Equip Eq. Eq ID Rw/Cl Spec. Spec Demd? OK? OK7 OK7 OK7 _Cl BS GRS Yes Yes N/A Yes Yes 8 10MOV-39A RHR A TORUS COOLING iSOL VALVE RB 242 67 3A 242.67 Yes RB 242.67 3D 242.67 Yes BS GRS Yes Yes N/A Yes Yes 8 10MOV-39B RHR B TORUS COOLING ISOL VALVE RB 242.67 2P 242.67 Yes BS GRS Yes Yes N/A Yes Yes 8 10MOV-66A RHR HEAT EXCH A BYPASS VALVE RB 242.67 2D 242 67 Yes BS GRS Yes Yes N/A Yes Yes 8 10MOV-668 RHR HEAT EXCH B BYPASS VALVE RB 227.50 3A 227.50 Yes BS GRS Yes Yes Yes Yes Yes 6 10P-3A RESIDUAL HEAT REMOVAL PUMP A RB 227.50 3D 227.50 Yes BS GRS Yes Yes Yes Yes Yes 6 10P-38 RESIDUAL HEAT REMOVM PUMP B RB 227.50 3A 227.50 Yes BS GRS Yes Yes Yes Yes Yes 6 10P-3C RESIDUAL HEAT REMOVAL PUMP C RB 227.50 3D 227.50 Yes BS GRS Yes Yes Yes Yes Yes 6 10P-3D RESIDUAL HEAT REMOVAL PUMP D RB 227.50 2A 227.60 Yes BS GRS Yes Yes N/A Yes Yes 7 10RV-41 A RHR PUMP A SHUTDOWN COOLING SUCT RELIEF VALVE RB 227.50 2D 227.50 Yes BS GRS Yes Yes N/A Yes Yes' 7 10RV-41R RHR PUMP B SHUTDOWN COOLING SUCT RELIEF VALVE RB 227.50 2A 227.50 Yes BS GRS Yes Yes N/A Yes Yes 7 10RV-41C RHR PUMP C SHUTDOWN COOLING SUCT RELIEF VALVE PJ3 227.50 20 227.50 Yes BS GRS Yes Yes N/A Yes Yes 7 10RV-41D RHR PUMP D SHUTDOWN COOLING SUCT RELIEF VALVE RB 242.67 1R 272.00 Yes BS GRS Yes Yes N/A Yes Yes 7 10SV-35A RHR LOOP A SAFETY VALVE RB 242.67 1W 272.00 Yes BS GRS Yes Yes N/A Yes Yes 7 10SV-358 RHR LOOP B SAFETY VALVE RB 326.75 6R 326 00 N/A DOC RRS No Yes Yes Yes No 0 11EV-14A SLC A DOUBLE SOUlB ACTIVATED SHEAR EXPLOSIVE VALVE RB 326.75 6R 326 00 N/A DOC RRS No Yes Yes Yes No 0 11EV-148 SLC B DOUBLE SOUlB ACTIVATED SHEAR EXPLOSIVE VALVE RB 326.75 6P 326 00 N/A ABS CRS Yes Yes Yes Yes Yes 5 11 P-2A STANDBY LIQUlO CONTROL A PUMP RB 326.75 6P 326 00 N/A ABS CRS Yes Yes Yes Yes Yes 5 11 P-2B STANDBY LIQUlO CONTROL B PUMP RB 326.75 6P 326.00 N/A ABS CRS Yes Yes N/A Yes Yes 7 11SV-39A SLC PUMP 2A DtSCH SAFETY VALVE RB 326.75 6P 326.00 N/A ABS CRS Yes Yes N/A Yes Yes 7 11SV-398 SLC PUMP 28 DISCH SAFETY VALVE RB 314 50 3R 326.00 N/A ABS CRS Yes Yes N/A Yes Yes 8 12MOV-18 RWCU SUPPLY OUTBD ISOL VALVE RB 242.67 4.A 242.67 Yes BS GRS Yes Yes Yes Yes Yes 18 25-01 CH A CORE SPRAY SYSTEM RACK RB 300 00 3.5 R 300 00 Yes BS GRS Yes Yes Yes Yes Yes_ 18 25-05 REACTOR PROTECTION AND NSSS SYSTEM RACK RB 300.00 5.5YW 300 00 Yes BS GRS Yes Yes Yes Yes Yes 18 25-05 REACTOR PROTECTION AND NSSS SYSTEM RACK HPCIINST RACK RB 242.67 1R 242.67 Yes BS GRS Yes Yes Yes Yes Yes 18 25-50 RHR CHANNEL A INST RACK RB 242.67 4A 242.67 Yes BS GRS Yes Yes Yes Yes Yes 18 25-59 Certification: Certification: All the information contained on this Screening Verification Data Sheet (SVDS) is, to the best of our The information provided to the Seismic Capabihty Engineers regarding systems and operations of knowledge and beikf correct and accurate. "All information* includes each entry and conclusion the equipment contained in the SVDS is, to the best of our knowledge and behef. correct and (whether venfied to be seismically adequate or not). accurate. Approved: (Signatures of all Seismic Capabihty Engineers on the Seismic Review Team (SRT) are Approved; (One signature of Systems or Operations Engineer is required if the Seismic Capabihty required, there should be atleast two on the SRT. All signatories should agree with all the entries Engineers deem it necessary.) tnd conclusions. One signatory should be a hcensed professional engineer.) l Mara Lakis l 0 ## l l l l l Pnnt or Type Name S e D te Pnnt or Type Name Sqnature Date Walter Djordjevic l l l l l l l Pnnt or Type Name Sgnature Dath Pnnt or Type Name Sgnature Date 1 I I I I l l Pnnt or Type Name Sqnature Date Pnnt or Type Name Sgnature Date
JAMES A. FITZPATRICK NUCLEAR POWER PLANT Page 14/26 SCREENING VERIFICATION DATA SHEET (SVDS) Eq. Eq. ID Sys/Eq. Dese Bldg. FI El. Rm or Base El. <40*7 Cap. Demd. Cap > C*veats Anchor interact Equip Cl Rw/Cl Spec. Spec Dernd? OK7 OK7 OK7 OK7 18 25-60 CORE SPRAY CHANNEL B INST RACK RB 242.67 4D 242.67 BS Yes GRS Yes Yes Yes Yes Yes 18 25-62 RHR CHANNEL B INST RACK RB 242.67 3D 242.67 Yes BS GRS Yes Yes Yes Yes Yes 7 66PCV-101 RB UNIT COOLERS SWS RETURN HEADER PRESS CONTROL RB 272.00 7.5 Y 272.00 Yes BS GRS Yes Yes N/A Yes Yes VALVE 7 566TCV-107E EAST CRESCENT AREA UC-22E SWS INLET TEMP CONTROL VALVE RB 242.67 3A 242.67 Yes BS GRS Yes Yes N/A Yes Yes 7 66TCV-107F WEST CRESCENT AREA UC-22F SWS INLET TEMP CONTROL RB 242.67 3D 242.o7 Yes BS GRS Yes Yes N/A Yes Yes VALVE 10 660C-22A WEST CRESCEe1T AREA UNIT COOLER 22A RB 242.67 1R 242.67 Yes BS GRS Yes Yes Yes Yes Yes 10 66UC-228 EAST CRESCENT AREA UNIT COOLER 228 RB 242.67 40 242.67 Yes BS GRS Yes Yes Yes Yes Yes 10 66UC-22C WEST CRESCENT AREA UNIT COOLER 22C RB 242.67 2.5 A 242.67 Yes BS GRS Yes Yes Yes Yes Yes 10 660C-22D EAST CRESCENT AREA UNIT COOLER 22D RB 242.67 3.5 D 242.67 Yes BS GRS Yes Yes Yes Yes Yes 10 66UC-22E WEST CRESCENT AREA UNIT COOLER 22E RB 242.67 3A 242.67 Yes BS GRS Yes Yes Yes Yes Yes 10 660C-22F EAST CRESCENT AREA UNIT COOLER 22F RB 242.67 30 242.67 Yes BS GRS Yes Yes Yes Yes Yes to 66UC-22G WEST CRESCENT AREA UNIT COOLER 22G RB 242.67 3.5 A 242.67 Yes BS GRS Yes Yes Yes Yes Yes 10 66UC-22H EAST CRESCENT AREA UNIT COOLER 22H RB 242.67 2.5 O 242.67 Yes BS GRS Yes Yes Yes Yes Yes 10 66UC-22J WEST CRESCENT AREA UNIT COOLER 22J RB 242.67 4A 242.67 Yes BS GRS Yes Yes Yes Yes Yes 10 66UC-22K HPCI ROOM UNIT COOLER 22K RB 242.67 1T 242.67 Yes BS GRS Yes Yes Yes Yes Yes to 67E-11 WEST CABLE TUNNEL VENT SUPPLY COOLING COIL EB 286.00 18.5 A 286.00 Yes BS GRS Yes Unk Unk Yes Unk 10 67E-14 EAST CABLE TUNNEL VENT SUPPLY COOLING COIL EB 286.00 18.5 A 286.00 Yes BS GRS Yes Unk Unk Yes Unk 7 67PCV-101 ELECTRIC BAY UC-16A & B SERVICE WATER RETURN PRESS EB 286.00 19 B 272.00 BS Yes GRS Yes Yes N/A Yes Yes CONTROL VALVE 10 67UC-16A WEST ELECTRIC BAY UNIT COOLER EB 286.00 17 A1 272.00 Yes BS GRS Yes No No Yes No - 10 67UC-16B EAST ELECTRIC BAY UNIT COOLER EB 286.00 17 8 272.00 Yes BS GRS Yes No No Yes No 10 70AHU-12A RELAY ROOM VENT AIR HANDLING UNIT A AD 300.00 9.5 2 300.00 N/A ABS CRS Yes No Unk Yes No 10 70AHU-128 RELAY ROOM VENT AIR HANDLING UNIT B AD 300.00 9.5 X 300.00 N/A ABS CRS Yes No Unk Yes No 10 70AHU-19A CHILLER ROOM VENT AIR HANDLING UNIT A AD 300.00 9S 300.00 N/A ABS CRS e Yes Yes Yes Yes Yes 10 70ANU-198 CHILLER ROOM VENT AIR HANDLING UNIT B AD 300.00 9S 300.00 N/A ABS CRS Yes Yes Yes Yes Yes CMA tion: Certrfication: All the information contained on this Screening Venfication Data Sheet (SVDS) is, to the best of our The information provided to the Seismic Capabihty Engineers regarding systems and operations of knowledge and belief, correct and accurate. "AR information" includes each entry and conclusion the equipment contained in the SVDS is, to the best of our knowledge and belief, correct and (whether venfied to be seismically adequate or not). accurate. [ Approved: (Signatures of all Seismic Capability Engineers on the Seismic Review Team (SRT) are Approved: (One signature of Systems or Operatior:s Engineer is required if the Seismic C required; there shouM be atleast two on the SRT. All signatories should agree with all the entries Engineers deem it necessary.) and conclusions. One signatory should be a licensed profess ~ nal engineer.) l Mara Lakis l l 8 l l l Pnnt or Type Name Signatu Date Pnnt or Type Name Sqnature Date l Walter Djordjevic Pnnt or Type Name I !/ V Mgns I l l l l Dat6 Pnnt or Type Name Signature Date [ l l I I I Pnnt or Type Name I l Segnature Date Pnnt or Type Name Signature Date
, [3 f)
JAMES A. FITZPATRICK NUCLEAR POWER PLANT Page 15/26 SCREENING VERIFICATION DATA SHEET (SVDS) Eq. Eq ID Sys/Eq. Desc Bldg. FI EL Rm or Base EL <407 Cap. Demd. Cap > Caveats Anchor interact Equip Cl Rw/Cl Spec. Spec Demd? OK? OK? OK7 OK? 10 70AHU-3A CONTROL ROOM VENT AIR HANDLING UNIT A AD 300 00 9.5 Z 300 00 N/A ABS CRS Yes No No Yes No 10 70AHU-3B CONTROL ROOM VENT AIR HANDLING UNIT B AD 300 00 95X 300 00 N/A ABS CRS Yes No No Yes No 10 70FD-1 RELAY ROOM INLET VENT FIRE DAMPER AD 300.00 10 C 300 00 N/A ABS CRS Yes Yes Yes Yes Yes 10 70FD-10 SOUTH / NORTH CABLE ROpMS FIRE DAMPER RR 284 67 95C 286.00 N/A /BS CRS Yes Yes Yes Yes Yes 19 70FD-2 RELAY ROOM VENT EXHAUST FANS INLET FIRE DAMPER AD 300 00 10 C 300.00 N/A ABS CRS Yes Yes Yes Yes Yes 10 70FD-4 RELAY ROOM VENT EXHAitJST FIRE DAMPER RR 284.67 95C 286 00 N/A ABS CRS Yes Yes Yes Yes Yes 10 70FD-5 RELAY ROOM VENT EXHAUST FIRE DAMPER RR 284 67 9.5 C 286 00 N/A ABS CRS Yes Yes Yes Yes Yes 10 70FD-6 RELAY ROOM VENT SUPPLY FIRE DAMPER 3R 284 67 10.5 C 286.00 N/A ABS CRS Yes Yes Yes Yes Yes 10 70FD-7 RELAY ROOM VENT EXHAUST FIRE DAMPER RR 284 67 10 5 C 286 00 N/A ABS CRS Yes Yes Yes Yes Yes 9 70FN-13A RELAY ROOM VENT EXHAUST FAN A AD 300 00 95Z 300.00 Yes BS GRS Yes Yes Yes Yes Yes 9 70FN-13B RELAY ROOM VENT EXHAUST FAN B AD 300 00 9.5 Z 300 00 Yes BS GRS Yes Yes Yes Yes Yes 9 70FN-4A CONTROL ROOM VENT EXHAUST FAN A AD 310.50 9.5 V 300.00 Yes BS GRS Yes Yes Yes Yes Yes 9 70FN-48 CONTROL ROOM VENT EXHAUST FAN B AD 310 50 95V 300 00 Yes BS GRS Yes Yes Yes Yes Yes 10 70 MOD-101 A RELAY ROOM VENT AHU-12A OUTLET ISOL DAMPER AD 300 00 95Z 300 00 N/A ABS CRS Yes Yes Yes Yes Yes 10 70 MOD-101B RELAY ROOM VENT AHU-12B OUTLET ISOL DAMPER AD 300 00 95x 300 00 N/A ABS CRS Yes Yes Yes Yes Yes 10 70 MOD-102A RELAY ROOM VENT EXHAUST FAN 13A OUTLET ISOL DAMPER AD 310.50 9.5 X 300 00 N/A ABS CRS Yes Yes Yes Yes Yes 10 70 MOD-1028 RELAY ROOM VENT EXHAUST FAN 138 OUTLET ISOL DAMPER AD 310 50 10 Z 300.00 N/A ABS CRS Yes Yes Yes Yes Yes 10 70 MOD-104A RELAY ROOM VENT REClRC ISOL DAMPER A AD 310 50 9.5 X 300 00 N/A ABS CRS Yes Yes Yes Yes Yes 10 70 MOO-1048 RELAY ROOM VENT RECIRC ISOL DAMPER B AD 310 50 9.5 X 300 00 N/A ABS CRS Yes Yes Yes Yes Yes 10 70 MOD-106A CONTROL ROOM VENT AHU-3A OUTLET ISOL DAMPER AD 300 00 9.5 2 300.00 N/A ABS CRS Yes Yes Yes Yes Yes 10 70 MOD-1068 CONTROL ROOM VENT AHU-38 OUTLET ISOL DAMPER AD 300 00 9.5 Z 300 00 N/A ABS CRS Yes Yes Yes Yes Yes 10 70 MOD-108A CONTROL ROOM VENT EXHAUST FAN 4A OUTLET ISOL DAMPER AD 310 t,0 9.5 V 300 00 N/A ABS CRS Yes Yes Yes Yes Yes 10 70 MOD-1088 CONTROL ROOM VENT EXHAUST FAN 4B OUTLETISOL DAMPER AD 310 50 95V 300 00 N/A ABS CRS Yes Yes Yes Yes Yes 10 70 MOD-110A CONTROL ROOM VENT RECIRC ISOL DAMPER A AD 310.50 9.5 V 300.00 N/A ABS CRS Yes Yes Yes Yes Yes 10 70 MOD-1108 CONTROL ROOM VENT RECIRC ISOL DAMPER B AD 310 50 9.5 V 300.00 N/A ABS CRS Yes Yes Yes Yes Yes 7 70PCV-100A1 CR/RR CHILLER CONDENSER A SWS PRESS CONTROL VALVE 1 AD 300 00 11 S 300 00 Yes BS GRS Yes Yes N/A Yes Yes Certification. Certification: All the information contained on this Screening Verification Data Sheet (SVDS) is, to the best of our The information provided to the Seismic Capabihty Engineers regarding systems and operations of knowledge and belief, correct and accurate. "All informaton" includes each entry and conclusion the equipment contained in the SVDS is, to the best of our knowledge and belief, correct and (whether venfied to be seismically adequate or not). accurate. Approved: (Signatures of all Seismic Capability Engineers on the Seismic Review Team (SRT) are Approved: (One signature of Systems or Operations Engineer is required if the Seismic Capabihty required; there should be atleast two on the SRT. All signatories should agree with all the entries Engineers deem it necessary.) and conclusions. One signatory should be a hcensed professional engineer.) l Mara Lakes l 10./ N# l l l l l Pnnt or Type Name S , at Date Pnnt or Type Name Sqnature Date l Walter Djordjevic l l M l l l l Pnnt or Type Name Sg ture # Date' Pnnt or Type Name Sqnature Date l I I I I I I Pnnt or Type Name Signature Date Pnnt or Type Name Sgnature Date
JAMES A. FITZPATRICK NUCLEAR POWER PLANT Page 16/26 SCREENING VERIFICATION DATA SHEET (SVDS) Eq. Eq. ID Sys/Eq. Desc Bldg. FI El. Rm or Base El. <40'? Cap. Demd. Cap > Caveats Anchor Interact Equip Cl Rw/Cl Spec. Spec Demd? OK7 OK? OK? OK? 7 70PCV-100A2 CR/RR CHILLER CONDENSER B SWS PRESS CONTROL VALVE 2 AD 300.00 11 S 300.00 Yes BS GRS Yes Yes N/A Yes Yes 7 70PCV-100B1 CR/RR CHILLER CONDENSER A SWS PRESS CONTROL VALVE 1 AD 300.00 10 V 300 00 Yes BS GRS Yes Yes N/A Yes Yes 7 70PCV-100B2 CR/RR CHILLER CONDENSER B SWS PRESS CONTROL VALVE 2 AD 300.00 10 V 300.00 Yes BS GRS Yes Yes N/A Yes Yes 7 70RV-101A CR/RR CHILLER A CONDElgSER SERVeCE WATER RELIEF VALVE AD 300 00 11 S 300.00 Yes BS GRS Yes Yes N/A Yes Yes 7 70RV-1018 CR/RR CHILLER B CONDENSER SERVICE WATER RELIEF VALVE AD 300.00 10 V 300.00 Yes BS GRS Yes Yes N/A Yes Yes AD 300.00 10 5 S 300 00 N/A ABS CRS Yes No No Yes No 11 70RWC-2A(CND) CONTROL ROOM CHILLEfM CONDENSER 11 70RWC-2B(CND) CONTROL ROOM CHILLER B CONDENSER AD 300.00 10.5 S 300.00 N/A ABS CRS Yes f(o No Yes No 1 7 70TCV-123A CR/RR CHILLER ROOM AHU-19A CHILLED WATER OUTLET TEMP AD 300.00 9.5 S 300.00 Yes BS GRS Yes No N/A Yes No CONTROL VALVE 7 70TCV-1238 CR/RR CHILLER ROOM AHU-198 CHILLED WATER OUTLET TEMP AD 300.00 9.5 S 300.00 Yes BS GRS Yes No N/A Yes No CONTROL VALVE 14 71ACA2 DISTRIBUTION PANEL 71 ACA2 EMERGENCY CONTROL & INST RR 284.67 11 C 286 00 Yes BS GRS Yes Yes Yes Yes Yes POWER A 1 71MCC-253 600V MOTOR CONTROL CENTER (BUS 125300) AD 300 00 10 C 300 00 N/A ABS CRS Yes No Yes Yes No 4 71PT-71ESSB1 SAFEGUARD BUS B DISTRIBUTION 15KVA TRANSFORMER 71MCC- BR 272.00 12 E 272.00 Yes BS GRS Yes Yes Yes Yes Yes 252-OB3 10 72AHU-30A BATTERY ROOM A AIR HANDLING UNIT BR 282.00 12 E 272.00 N/A ABS CRS Yes Yes Yes Yes Yes 10 72AHU-308 BATTERY ROOM B AIR HANDLING UNIT BR 282.00 12 G 272.00 N/A ABS CRS Yes Yes Yes Yes Yes 72FD-13 BATTERY ROOM A VENT EXHAUST FANS A & C SUCT FIRE BR 282.00 13 E 272.00 N/A ABS CRS Yes Yes Yes Yes Yes 10 DAMPER 72FD-14 BATTERY ROOM B VENT EXHAUST FANS B & D SUCT FIRE BR 282.00 13 F 272.00 N/A ABS CRS Yes Yes Yes Yes Yes 10 DAMPER 72FD-3 BATTERY ROOM A VENT EXHAUST FANS A & C DISCH FIRE BR 282.00 13 E 272.00 N/A ABS CRS Yes Yes Yes Yes Yes 10 DAMPER 72FD-4 BATTERY ROOM A RECIRC FAN A EXHAUST FIRE DAMPER BR 282 00 12.5 E 272.00 N/A ABS CRS Yes Yes Yes Yes Yes 10 72FD-5 BATTERY ROOM VENT AHU-30B SUPPLY FIRE DAMPER BR 272.00 12 G 272.00 N/A ABS CRS Yes Yes Yes Yes Yes 10 72FD-6 BATTERY ROOM A AHU-30A INLET FIRE DAMPER BR 282.00 12.5 E 272.00 N/A ABS CRS Yes Yes Yes Yes Yes 10 Certification: Certification: AH the information contained on this Screening Verification Data Sheet (SVDS) is, to the best of our The information provided to the Seismic Capabihty Engineers regarding systems and operations of knowledge and belief, correct and accurate. "An information" includes each entry and conclusion the equipment contained in the SVDS is, to the best of our knowledge and behef, correct and (whether venfied to be seismically adequate or not). accurate. Approved: (Signatures of au Seismic Capabihty Engineers on the Seismic Review Team (SRT) are Approved: (One signature of Systems or Operattons Engineer is required if the Seismic Capability required; there should be atieast two on the SRT. AH signatories should agree with all the entries Engineers deem it necessary.) and conclusions. One signatory should be a licensed professionalengineer.) l Mara Lakis l W d l l l l Pnnt or Type Name Signature Date Pnnt or Type Name Sgnature Date Walter Djordjevic l l l l l l l Pnnt or Type Name Sgn ure ' Dafe Pnnt or Type Name Sgnature Date I I I I I i I Pnnt or Type Name Sqnature Date Pnnt or Type Name Sgnature Date
. _ _ _ _ . . _ .. .~m_. -- - . . _ .__ _ _ . ._ .- _ . . . _ _ _ _ _ _ . _ _ _
O O O
- JAMES A. FITZPATRICK NUCLEAR POWER PLANT Page 1T/26 SCREENING VERIFICATION DATA SHEET (SVDS)
Sys/Eq. Desc Birig. FI El. Rm or Base El. <4c? Cap. Demd. Cap > Caveats Anchor interact Equip Yq Eq.ID Spec. Spec Pmnd? OK? OK7 OK7 OK? Rw/Cl Cl BR 282.00 12 E 272 00 N/A ABS CRS Yes Yes Yes Yes Yes 9 72FN-31A EATTERY ROOM A REClRC FAN BR 282.00 12 F 272.00 N/A ABS CRS Yes Yes Yes Yes Yes 9 72FN-318 BATTERY ROOM B RECIRC FAN BR 282.00 12 E 272.00 N/A ABS CRS Yes No Yes Yes No 9 72FN-46A BATTERY ROOM A EXHAUST FAN BR 282.00 12 F 272 00 N/A ABS CRS Yes No Yes Yes No - 9 72FN-468 BATTERY ROOM B EXHAL ST FAN BR 282.00 12 E 272.00 N/A ABS ORS Yes No Yes Yes No f 9 72FNE BATTERY ROOM A EXHAt._ST FAN Yes Yes Yes Yes BR 282.00 12 F 272.00 N/A ABS CRS Yes 9 72FNJ60 BATTERY ROOM D EXM^? ST FAN BR 282.00 12 E 272.00 N/A ABS Cr<S Yes Yes Yes Yes Yes f 10 72 MOD-102A BATTERY ROOM A RECIRC FAN A OfSCH ISOL DAMPER BR 282.00 12 F 272.00 N/A ABS CRS Yes Yes Yes Yes Yes ! to 72 MOD-102B BATTERY ROOM B RECIRC FAN B DISCH ISOL DAMPER BR 282.00 12 E 272.00 N/A ABS CRS Yes Yes Yes Yes Yes 10 72 MOD-104A BATTERY ROOM A VENT RECtRC FAN A EXHAUST DAMPER BR 282.00 12 F 272.00 N/A ABS CRS Yes Yes Yes Yes Yes 10 72 MOD-104B BATTERY ROOM B VENT RECIRC FAN B EXHAUST DAMPER RB 344.50 5.5 F 344.00 N/A ABS CRS Yes No Yes Yes No 15 71 BAT-3A LPCI INVERTER BATTERY RB 344.50 2W 344 00 N/A ABS CRS Yes No Yes Yes No 15 71 BAT-38 LPCI INVERTER BATTERY Yes Yes BR 272.00 12.5 E 272 00 Yes BS GRS Yes Yes Yes 16 71BC-1 A 125 VDC STATION BATTERY CHARGER BR 272.00 12.5 F 272.00 Yes BS GMS Yes Yes Yes Yes Yes 16 71BC-1B 125 VDC STATION BATTERY CHARGER BR 272.00 13 C 272.00 N/A ABS CRS Yes No No Yes No 14 718CB-2A BATTERY A CONTROL BOARD BR 272.00 13 G 272.00 N/A -ABS CRS Yes No No Yes No 14 718CB-28 BATTERY B CONTROL BOARD BR 272.00 12 E 272.00 Yes BS GRS Yes No No Yes No f 15 7168-1 125 VOLT STATION BATTERY A BR 272.30 12 F 272.00 Yes BS GRS Yes No Yes Yes No , 15 71SB-2 125 VOLT STATION BATTERY B Cett6 cation: ' Certification: AM the information contained on this Screening Venfication Data Sheet (SVDS) is, to the best of our The information provided to the Seismic Capabibty Engineers regarding systems and operations of knowledge and behef, correct and ocurate. *AN information" includes each entry and conclusion the equipment contained in the SVDS is, to the best of our knowledge and behef, correct and (whether venfied to be seismically adequate or not). accurate. Approved. (Sgnatures of all Se:smic Capabdity Engineers on the Seismic Review Team (SRT) are Approved: (One signature of Systems or Operations Engineer is required if the Seismic Capabihty requireo; there should be atleast two on the SRT. All signatories should agree with all the entries Engineers deern it necessary.) and conclusions. One sgnatory should be a licensed professionagengineer.) l Hara Lakis l d l l . l l l Fnnt or Type Name Sign ure Oate Pnnt or hw T4me Srsnature Date l Walter Djordrevic l l }l l l l ! Pnnt or Type Name Sgrfst Dat6 Pnnt or Type Name Sgnature Date l l l l l l l Pnnt or Type Name Sqnature Date Pnnt or Type Name Sgnature Date i
Os s
)
JAMES A. FITZPATRICK NUCLEAR POWER PLANT Page 18/26 SCREENING VERIFICATION DATA SHEET (SVDS) Eq Eq ID Sys/Eq. Desc Bldg. FI El. Rm or Base El. <40'? Cap. Demd. Cup > Caveats Anchor interact Equip Cl Rw/Cl Spec. Spec Demd? OK7 OK7 OK7 OK7 14 71ACUPS DISTRIBUTION PANEL 71 ACUPS UNINTERRUPTABLE BUS RR 284.67 11 F 286.00 Yes BS GRS Yes Yes Yes Yes Yes 14 71ACUPS-1 DISTRIBUTION PANEL 71 ACUPS-1 UNINTERRUPTABLE BUS RR 284.67 11 F 286.00 Yes BS GRS Yes Yes Yes Yes Yes 4 71PT-71 ACUPS UN!NTERRUPTABLE BUS 37.5KVA TRANSFORMER 71MCC-252-002 EB 272.00 14 A 272.00 Yes BS GRS Yes Yes Yes Yes Yes 20 71UPP UNINTERUPPTABLE BUS Mp SET 710PS-1 CONTROL PANEL EB- 272.00 14 B 272.00 N/A ABS CRS Yes Yes Unk Yes Unk , 13 71UPS-1 UNINTERRUPTABLE BUS MG SET 71UPS-1 EB 272.00 14 8 272.00 N/A ABS CRS Yes Yes Unk Yes Unk ' 3 i Certrhca ion: Certification-AB the informaton contained on this Screening Venfication Data Sheet (SVDS) is, to the best of our The information provided to the Seismic Capabihty Engineers regarding systems and operations of
\nowledge and belief, correct and accurate. "An information" includes each entry and conclusion the equipment contained in the SVDS is, to the best of our knowledge and behef, correct and (whether verfied to be setsmically adequate or not). accurate.
Approved. (Signatures of all Seismic Capsoddy Engineers on the Seismic Review Team (SRT) are Appoved: (One sgnature of Systems or Operations Engineer is required if the Seismic Capabihty required there should be atleast two on the SRT. AM signatories should agree with all the entnes Engineers deem it necessary.) and conclusons One signatory should be a sed p sional engineer.) l Pnd Okr. l l Ybl l l l Pnnt or Typs m'e Sqnature / Date Pnnt or Type Name Signature Drte l Doug Huwe l
' N lMut SM5 i i i i Pnnt or Type Name " Q Signature Date Pnnt or Type Name Sqnature Date i I I I I I l Pnnt or Type Name Sgnature Date Pnnt or Type Narne Signeure Date
O ( 3 Page 19/26 JAMES A.FITZPATRICK NUCt. EAR POWER PLANT SCREENING VERIFICATION DATA SHEET (SVDS) Sys/Eq. Desc Bldg. FI EL Rmor Base El <40'? Cap. Demd. Cap > Caveats Anchor interact Equip Eq Eq ID Spec. Spec Demd? OK? OK? OK? OK? Rw/Cl Cl Yes SU 262.00 7W 272.00 Yes BS GRS Yes Yes N/A Yes 8 23MOV-19 HPCI PUMP DISCH TO REACTOR INBD ISOL VALVE RB 262.42 5T 272.00 Yes BS GRS Yes Yes N/A Yes Yes 8 23MOV-21 HPCI FULL FLOW TEST RETURN TO CST 33TK-1 A & B UPSTR ISOL VALVE SU 257.08 4D 272.00 Yes BS GRS Yes Yes N/A Yes Yes 8 23MOV-25 HPCI MAIN PUMP P-1M Mly FLOW ISOL VALVE SU 227.50 1T 227.50 Yes BS GRS Yes Yes N/A Yes Yes e 23MOV-58 HPCI BOOSTER PUMP P-1B SUCT FROM SUPPRESSION POOL UPSTR ISOL VALVE ,l$ SU 262.00 2T 272.00 Yes BS GRS Yes Yr1 N/A Yes Yes 7 27AOV-131 A CAD TRAIN A NITROGEN MAKE-UP ISOL VALVE SU 262.00 2T 272.00 Yes BS GRS Yes Yes N/A Yes Yes 7 27AOV-131B CAD TRAIN B NITROGEN MAKE-UP ISOL VALVE SU 262 00 2T 272.00 Yes BS GRS Yes Yes N/A Yes Yes 7 27AOV-132A CAD TRAIN A TORUS NITROGEN MAKE-UP ISOL VALVE SU 262.00 2T 272.00 Yes BS GRS Yes Yes N/A Yes Yes 7 27AOV-1328 CAD TFAIN B TORUS NITROGEN MAKE-UP iSOL VALVE l Certificaton: Certrfication: Au the informaton contained on this Screening Venfication Data Sheet (SVDS) is, to the best of our The informaton provided to the Setsmic Capabildy Engineers regarding systems and operatens of knowledge and belief, correct and accurate. "AH information" includes each entry and conclusion the equipment contained in the SVDS is, to the best of our knowledge and belief, correct and (whether venfed to be seismicaHy adequate or not). accurate. Approved: (Sgnatures of au Seesmic Capability Engineers on the Setsmic Revew Team (SRT) are Approved: (One sgnature of Systems or Operatens Engineer is required if the Seismic Capability required, there should be atleast two on the SRT. AM signatories should agree with au the entnes Engineers deem it necessary.) and conclusons. One signatory should be a lice . pro sional engineer.) Prid Okas l l l l l l l Sgnature Date
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Pnnt or Type Name Signa re 'I Date Pnnt or Type Name
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l Robert Kester l l 2/ [ l l Sqnature l Date
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Pnnt or Type Name ~Sgnafure 'Dafe Pnnt or Type Name l Steve Anagnostrs
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7 Sgrfillure
~l T/23
' Date Pnnt or Type Name l
Sgnature l Date l , Pnnt or Type Name f
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JAMES A FITZPATRICK NUCLEAR POWER PLANT Page 20/26 SCREENING VERIFICATION DATA SHEET (SVDS) Eq Eq ID Sys/Eq. Desc Bkig FI EL Rm or Base EL <40*? Cap. Demd. Cap > Caveats Anchor Interact Equip CI Rw/Cl Spec. Spec Demd? OK7 OK7 OK7 OK7 7 27AOV-126A AMBIENT VAPORIZER A INLET VALVE CB 271.67 .5 RP 272.00 Yes BS GRS Yes Yes N/A Yes Yes 7 27AOV-126B AMBIENT VAPORIZER 8 INLET VALVE CB 271.67 .5TW 272.00 Yes BS GRS Yes Yes N/A Yes Yes 7 27AOV-127A STEAM VAPORIZER NV-8 LIQUID NITROGEN SUPPLY VALVE CB 272.00 .5 RP 272.00 Yes BS GRS Yes Yes N/A Yes Yes 7 27AOV-127B STEAM VAPORIZER NV-8 IJOUID NITROGEN SUPPLY VALVE CB 272.00 .5TW 272.00 Yes BS GRS Yes Yes N/A Yes Yes 7 27AOV-128A CAD TRAIN A NITROGEMl@AKE-UP SUPPLY VALVE CB 272.00 272.00 Yes BS GRS Yes Yes N/A Yes Yes 7 27AOV-129A DRYWELL PCV AND INS 3WCAD TRAIN A BACKUP VALVE CB 271.67 .5 RP 272.00 Yes BS GRS Yes Yes N/A Yes Yes 18 27EH-10A CAD A AMBIENT VAPORIZER ELECTRIC HEATER CB 271.67 .5 RT 272.00 Yes BS GRS Yes Yes Yes Yes Yes 18 27EH-10B CAD B AMBIENT VAPORIZER ELECTRIC HEATER CB 271.67 .5 RT 272.00 Yes BS GRS Yes Yes Yes Yes Yes 18 27NS-CA CAD A NITROGEN SUPPLY INSTR CABINET CB 271.67 .5RP 272.00 Yes BS GRS Yes Yes Yes Yes Yes 18 27NS-CB CAD B NITROGEN SUPPLY INSTR CABINET CB 271 67 34 TW 272.00 Yes BS GRS Yes Yes Yes Yes Yes 7 27PCV-122A PRESS BUILDING COIL A INLET PRESS CONTROL VALVE CB 271.67 .5RP 272.00 Yes BS GRS Yes Yes N/A Yes Yes 7 27PCV-122B PRESS BUILDING COIL B INLET PRESS CONTROL VALVE CB 271.67 .5TW 272.00 Yes BS GRS Yes Yes N/A Yes Yes 7 27PCV-134A CAD TRAIN A VALVE OPERATING NITROGEN PRESS CONTROL CB 271.67 .5 RP 272.00 Yes BS GRS Yes Yes N/A Yes Yes VALVE 7 27PCV-1348 CAD TRAIN B VALVE OPERATING NITROGEN PRESS CONTROL CB 271.67 .5TW 272.00 Yes BS GRS Yes Yes N/A Yes Yes VALVE 7 27PCV-140 DRYWELL PCV AND INSTR NITROGEN BACKUP SUPPLY PRESS CB 272.00 1 PR 272.00 Yes BS GRS Yes Yes N/A Yes Yes CONTROL VALVE 7 27RV-101 A LIQUID NITROGEN TANK A RELIEF VALVE CB 271 67 .5RP 272 00 Yes BS GRS Yes Yes N/A Yes Yes 7 27RV-101B LIQUlO NITROGEN TANK B RELIEF VA'.VE CB 271.67 .5TW 272.00 Yes BS GRS Yes Yes N/A Yes Yes y 27SV-114A CAD TRAIN A VALVE OPERATING SUPPLY SAFETY VALVE CB 271.67 .5 RP 272 00 Yes BS GRS Yes Yes N/A Yes Yes 7 27SV-1148 CAD TRAIN B VALVE OPERATING SUPPLY SAFETY VALVE CB 271.67 .5TW 272.00 Yes BS GRS Yes Yes N/A Yes Yes 7 27SV-115A AMBIENT VAPORIZER A OUTLET SAFETY VALVE CB 271.67 .5RP 272.00 Yes BS GRS Yes Yes N/A Yes Yes 7 27SV-115B AMBIENT VAPORIZER B OUTLET SAFETY VALVE CB 271 67 .5TW 272.00 Yes BS GRS Yes Yes N/A Yes Yes 7 27SV-118A LIQUID NITROGEN TANK A OUTLET SAFETY VALVE CB 271 67 .5RP 272.00 Yes BS GRS Yes Yes N/A Yes Yes 7 27SV-1188 LIQUlO NITRCGEN TANK B OUTLET SAFETY VALVE CB 271 67 .5TW 272 00 Yes BS GRS Yes Yes N/A Yes Yes 7 27SV-119A PRESS BUILDING COIL A INLET SAFETY VALVE CB 271.07 .5 RP 272.00 Yes BS GRS Yes Yes N/A Yes Yes Certificaten Certrfication: All the informaton contained on this Screening Venficaton Data Sheet (SYDS) is, to the best of our The information provided to the Seismic Capabihty Engineers regarding systems and operations of h.@ and behef, correct arid accurate. "All informaten" includes each entry and conclusion the equipment contained in the SVDS is, to the best of our knowledge and belief, correct and (wnether venfied to be seismecally adequate or not). accurate. Approved (Sqnatures of all Seismic Capabihty Engineers on the Seismic Review Team (SRT) are Approved. (One sgnature of Systems or Operations Engineer is required if the Seismic Capabihty requred, there should be atleast two on the SRT. All sgnatories should agree with all the entries Engineers deem it necessary.) and conclusens. One signatory should be a hcensed profess' al engineer.) l Pnd Okas l lf l l l l SqnaNre Date
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Pnnt or Type Name Sqnature '/ /Date Pnnt or Type Name [ Mara Lakrs l v W D# l l l l l Pnnt or Type Name Sgnature Date Pnnt or Type Name Sqnature Date l Steve Anagnostrs l
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# Dde Pnnt or Type Name l
Sgnature l Date l Pnnt or Type Name f SgnsfUre
O O O Page 21/26 JAMES A. FITZPATRICK NUCLEAR POWER PLANT SCREENING Vt:RIFICATION DATA SHEET (SVDS) Sys/Eq Desc Bldg. F1 EL Rm or Base El. <407 Cap. Demd. Cap > Caveats Anchor Interact Eqesp Eq. Eq ID Spec. Spec Demd? OK7 OK? OK7 OK7 Rw/Cl Cl Yes Yes CB 271.67 .5 TW 272.00 Yes BS GRS Yes Yes N/A 7 27SV-1198 PRESS BUILDING COIL B INLET SAFETY VALVE CB 271.67 .5TW 272.00 Yes BS GRS Yes Yes N/A Yes Yes 7 27SV-121 DRYWELL PCV AND INSTR NORMAL St;PPLY 27PCV-120 BYPASS SAFETY VALVE CB 271.67 .5TW 272.00 Yes BS GRS Yes Yes N/A Yes Yes 7 27SV-122 STEAM VAPORIZER NV-8 p TRAINS A & B INLET CROSS-TIE SAFETY VALVE - CB 271.67 .5TW 272.00 Yes BS GRS Yes Yes N/A Yes Yes 7 27SV-201A DRYWELL PCV AND INSISNORMAL SUPPLY SAFETY VALVE Yes CB 271.67 .5TW 272.00 Yes BS GRS Yes Yes N/A Yes 7 27SV-2018 ORYWELL PCV AND INSTR NOPMAL SUPPLY SAFETY VALVE CB 272.00 1 RT 272.00 Yes BS GRS Yes Yes N/A Yes Yes 7 27SV-202 DRYWELL PCV AND INSTR BACKUP SUPPLY SAFETY VALVE Certif%ation: Certification: AB the information contained on this Screening Venfication Data Sheet (SVDS) is, to the best of our The information provided to the Seismic Capability Engineers regarding systems and operations of knowledge and behef, correct and accurate. "AN information" includes each entry and conclusion the equipment contained in the SVDS is, to the best of our knowledge and belief, correct and (whether venfied to be seismicahy adequate or not). accurate. Approved. (Sgnatures of au Seismic Capabdity Engineers on the Seismic Review Team (SRT) are Approved. (One signature of Systems or Operations Engineer is required if :he Seismic Capability required; there should be atleast two on the SRT. All signatories should agree with au the entries Engineers deem it necessary.) and conclusions. One signatory should be a licensed pro sional engineer.) l Pnst Oitas l ' Mb f Sgnatdre l [
'/ Date l
Pnnt or Type Name l Signature l Gate l Pnnt or Type Name l Mara Lakis l d(d/ *- M/# l l l l l Pnnt or Type Name Signature Date Pnnt or Type Name Segnature Date l Steve Anag mtis l ) T/ D l l l l
/ Sigr(ature # Date Pnnt or Type Name Sgnature Date Pnnt or Type Name [
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(vl \ v l JAMES A. FITZPATRICK NUCLEAR POWER PLANT Page 22/26 SCREENING VERIFICATION DATA SHEET (SVDS) Eq Eq ID Sys/Eq Ds:c Bldg. Fl El. Rm or Base El. <40'? Cap Demd. Cap > Caveats Anchor Interact Equip Cl Rw/Cl Spec. Spec Demd? OK? OK? OK? OK? 18 33LT-101 CONDENSATE STORAGE TANKS LEVEL XMITTER YD 257.00 NA NA 272.00 Yes TS GRS Yes Yes Yes Yes Yes 14 71DC-84 DISTRIBUTION PANEL 71DC-84 DC CONTROL POWER B EG 272.00 27 A 272.00 Yes BS GRS Yes Yes Yes Yes Yes 10 92CD-1 EDG A SWITCHGEAR AREA VENT CO2 ISOL DAMPER EG 272.00 24.5 A1 300 00 Yes BS GRS Yes Yes Yes Yes Yes 10 92CD-2 EDG B SWITCHGEAR ARES VENT CO2 ISOL DAMPER EG 272.00 24.5 At 300 00 Yes BS GRS Yes Yes Yes Yes Yes 10 92CD-3 EDG C SWITCHGEAR AREA VENT CO2 ISOL DAMPER EG 272.00 24.5 A1 300 00 Yes BS GRS Yes Yes Yes Yes Yes 10 92CD-4 EDG D SWITCHGEAR ARfR VENT CO2 ISOL DAMPER EG 272.00 24.5At 300.00 Yes BS GRS Yes Yes Yes Yes Yes 10 92FD-10 EMERG DtESEL GEN VENT SUPPLY FANS B & D FRESH AIR SUCT EG 272.00 28 A1 300 00 N/A ABS CRS Yes Yes Yes Yes Yes FIRE DAMPER 10 92FD4 EMERG DIESEL GEN VENT SUPPLY FAN 8 DISCH FIRE DAMPER EG 272.00 25.5 At 300.00 N/A ABS CRS Yes Yes Yes Yes Yes 10 92FD-7 EMERG DIESEL GEN VENT SUPPLY FAN B RECIRC SUCT FIRE EG 272.00 26.5 At 300.00 N/A ABS CRS Yes Yes Yes Yes Yes DAMPER 10 92FD-8 EMERG DIESEL GEN VENT SUPPLY FAN D DISCH FIRE DAMPER EG 272 00 27 At 300.00 N/A ABS CRS Yes Yes Yes Yes Yes 10 92F D-9 EMERG DtESEL GEN VENT SUPPLY FAN D RECIRC SUCT FIRE EG 272.00 27.5 A1 300.00 N/A ABS CRS Yes Yes Yes Yes Yes DAMPER 20 92HV-9A EDG VENT A & C HEATING / VENT LOCAL CONTROL PANEL EG 272.00 23 A1 272.00 Yes BS GRS Yes Yes Yes Yes Yes 20 92HV-98 EDG VENT B & D HEATING / VENT LOCAL CONTROL PANEL EG 272.00 25.5 A1 272.00 Yes BS GRS Yes Yes Yes Yes Yes 10 92 MOD-143B EMERG DIESEL GEN 8 VENT EXHAUST ISOL DAMPER EG 272.00 26.5 A4 300 00 N/A ABS CRS Yes Yes Yes Yes Yes 10 92 MOD-143D EMERG DIESEL GEN D VENT EXHAUST ISOL DAMPER EG 272.00 27 A4 300 00 N/A ABS CRS Yes Yes Yes Yes Yes 10 92 MOD-1488 EMERG DIESEL GEN VENT SUPPLY FAN B RECtRC SUCT ISOL EG 272.00 26.5 A1 300.00 N/A ABS CRS Yes Yes Yes Yes Yes DAMPER 10 92 MOD-148D EMERG DIESEL GEN VENT SUPPLY FAN D RECtRC SUCT ISOL EG 272.00 27.5 A1 300.00 N/A ABS CRS Yes Yes Yes Yes Yes DAMPER 4 10 92 MOD-1498 EMERG DIESEL GEN VENT SUPPLY FAN B FRESH AIR SUCT ISOL EG 272.00 26.5 A1 300.00 N/A ABS CRS Yes Yes Yes Yes Yes DAMPER 10 92 MOD-1490 EMERG DIESEL GEN VENT SUPPLY FAN D FRESH AIR SUCT ISOL EG 272.00 27.5 A1 300 00 N!A ABS CRS Yes Yes Yes Yes Yes DAMPER Cert 6caten: Cert 6 cation: All the information contained on this Screening Venfication Dats Sheet (SVDS) is, to the best of our The information provided to the Seismic Capability Engineers regarding systems and operations of knowiedge and betef, correct and accurate *All information" includes each entry and conclusion the equipment contained in the SVDS is, to the best of our knowledge and belef, correct and (whether .enfied to be seismicah adeqaate or not). accurate. Approved (Sgnatures of all Seismic Capabihty Engineers on the Seismic Review Team (SRT) are Approved. (One signature of Systems or Operations Engineer is required if the Sersmic Capabdity required, there shouM be atleast two on the SRT. All signatories should agree with all the entnes Engineers deem it necessary ) and conclusons. One signatory should be a licensed profe ional engineer ) l Pn4 Okas Pnnt or Type Name l ~lh b ~ Sqnature l
// Oate l
Pnnt or Type Name l Sgnature l Date l l Steve Anagnostis
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l d~Ml r l l l
/ Synature / Datd Pnnt or Type Name Sgnature Date Pnnt or Type Name f i I I I I I I Pnnt or Type Name Sgnature Date Pnnt or Type Name Sqnature Date
r % e ( ! L . \ JAMES A. FITZPATRICK NUCLEAR POWER PLANT Page 23/26 SCREENING VERIFICATION DATA SHEET (SVDS) Eq. Eq ID Sys/Eq. Dese Bldg. FI El. Rmor Base El. <40"? Cap. Demd. Cap > Caveats Anchor interact Equip Cl Rw/Cl Spec. Spec Demd? OK7 OK? OK7 OK7 10 92 MOD-1500 EMERG DIESEL GEN VENT SUPPLY FANS B & D FRESH AIR WEST EG 272.00 28 A2 300.00 N/A ABS CRS Yes Yes Yes Yes Yes SUPPLY ISOL DAMPER 10 92 MOD-1500 EMERG DIESEL GEN VENT SUPPLY FANS B & D FRESH AIR EAST EG 272.00 28 A2 300.00 N/A ABS CRS Yes Yes Yes Yes Yes SUPPLY ISOL DAMPER v 19 92RTD-101 A EMERG DIESEL GEN A ROOM SOUTH SIDE RESIST TEMP EG 272.00 23 A2 300.00 Yes BS GRS Yes Yes N/A .Yes Yes DETECTOR .i 19 92RTD-1018 EMERG DIESEL GEN B ROOM SOUTH SIDE RESIST TEMP EG 272.00 27 A2 300 00 Yes BS GRS Yes Yes N/A Yes Yes DETECTOR 19 92RTD-101C EMERG DIESEL GEN C ROOM NORTH SIDE RESIST TEMP EG 272.00 25 A4 300.00 Yes BS GRS Yes Yes N/A Yes Yes DETECTOR 19 92RTD-101D LMERG DIESEL GEN D ROOM NORTH SIDE RESIST TEMP EG 272.00 24.5 A4 300.00 Yes BS GRS Yes Yes N/A Yes Yes DETECTOR 20 93AURP-02 EDG B & D AUX UNDERVOLTAGE RELAY P/,NEL EG 272.00 24.5 A 272.00 Yes BS GRS Yes Yes Yes Yes Yes 17 93EDG-8 EMERGENCY DIESEL GENERATOR B EG 272.00 26 5 A2 272.00 Yes BS GRS Yes Yes Yes Yes Yes 17 93EDG-D EMERGENCY DIESEL GENERATOR D EG 272.00 25 A2 272.00 Yes BS GRS Yes Yes Yes Yes Yes 20 93EGP-B EDG B GENERATOR CONTROL PANEL EG 272.00 26.A1 272.00 Yes BS GRS Yes Yes Yes Yes Yes 20 93EGP-D EDG B GENERATOR CONTROL PANEL EG 272.00 27,A1 272.00 Yes BS GRS Yes Yes Yes Yes Yes 20 93FPBD EDG B & D FORCED PARALLELING PANEL EG 272.00 26.5,A 272.00 Yes BS GRS Yes Yes Yes Yes Yes S 93P1-B1 EMERGENCY DIESEL GENERATOR B FUEL OIL TRANSFER PUMP EG 272.00 26.5 A4 272.00 Yes BS GRS Yes Yes Yes Yes Yes B1 5 93P1-82 EMERGENCY DIESEL GENERATOR B FUEL OIL TRANSFER PUMP EG 272.00 26.5 A4 272.00 Yes BS GRS Yes Yes Yes Yes Yes B2 5 93P1-01 EMERGENCY DIESEL GENERATOR 0 FUEL OIL TRANSFER PUMP EG 272.00 26.5 A4 272.00 Yes BS GRS Yes Yes Yes Yes Yes D1 5 93P1-D2 EMERGENCY DIESEL GENERATOR D FUEL OIL TRANSFER PUMP EG 272.00 26.5 A4 272.00 Yes BS GRS Yes Yes Yes Yes Yes D2 3 71DSC-11661 L16 UNIT SUBSTATION TRANSF T-14 HIGH SIDE DISC SW RB 300 00 6P 300 00 Yes BS GRS Yes Yes Yes Yes Yes Certrhcaten: Certification: All the informaton contained on this Screenmg Venfication Data Sheet (SVDS) is, to *be best of our The information provided to the Seismic Capability Engineers regarding systems and operations of knowledge and belief, correct and accurate. "All information" includes each entry and conclusion the equpment contained in the SVDS is, to the best of our knowledge and behef, correct and (whether venfied to be seismically adequate or not). accurate. Approved. (Signatures of all Setsmic Capabihty Engineers on the Seismic Review Team (SRT) are Approved: (One signature of Systems or Operations Engineer is required if the Seismic Capabihty required, there should be atleast two on the SRT. All signatories should agree with all the entries Engmeers deem it necessary.) and conclusens. One signatory should be a licensed prr sional engineer.) l Pnit Okas l lf l l l l Pnnt or Type Name Signature 'I Date Pnnt or Type Name Signature Date l Steve Anagnostis l Sb[ l l l
/ Dat6 Pnnt or Type Name Sgnature Date Pnnt or Type Name [ [ 5"(nature l l l l l l l Pnnt or Type Name Signature Date Pnnt or Type Name Sqnature Date
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JAMES A. FITZPATRICK NUCLEAR POWER PLANT Page 24/26 SCREENING VERIFICATION DATA SHEET (SVDS) Eq Eq ID Sys/Eq. Desc Bldg. FI El. Rm or Base El. <40*? Cap. Demd. Cap > Caveats Anchor interact Equap Cl Rw/Cl Spec. Spec Demd? OK? OK? OK7 OK? 3 71DSC-12661 L26 UNIT SUBSTATION TRANSF T-16 HIGH SIDE DISC SWITCH EB 272 00 18.5 B 272.00 Yes BS GRS Yes Yes Yes Yes Yes 3 71H06 4160V SWITCHGEAR DISTRIBUTION (BUS 10600) EG 272.00 27 A1 272.00 Yes BS GRS Yes Yes Yes Yes Yes 4 71T-14 600V UNIT SUBSTATION L16 TRANSFORMER RB 300.00 6P 300.00 Yes BS GRS Yes Yes Yes Yes Yes 4 71T-15 SWITCHGEAR L25100KVAaTRANSFORMER 71-10560 EB 272.00 19 AB 272.00 Yes BS GRS Yes Yes Yes Yes Yes 9 92FN-1A EMERG DIESEL GEN A VENT SUPPLY FAN EG 272.00 24 A1 300.00 N/A ABS CRS Yes Yes Yes Yes Yes 9 92FN-1B EMERG DIESEL GEN B VERT SUPPLY FAN EG 272.00 26 At 300_00 N/A ABS CRS Yes Yes Yes Yes Yes , 9 92FN-1C EMERG DIESEL GEN C VENT SUPPLY FAN EG 272.00 25 A1 300 00 N/A ABS CRS Yes Yes Yes Yes Yes 9 92FN-1D EMERG DIESEL GEN D VENT SUPPLY FAN EG 272.00 27 A 300 00 N/A ABS CRS Yes Yes Yes Yes Yes 20 93ECP-B EDG B ENGINE CONTROL PANEL EG 272.0G 26 A3 272.00 Yes BS GRS Yes Yes Yes Yes Yes ! 20 93ECP-O EDG D ENGINE CONTROL PANEL EG 272.00 27 A1 272.00 Yes BS GRS Yes Yes Yes Yes Yes 20 93ECSP-B EDG B ENGINE CONTROL SUB PANEL EG 272.00 26,A3 272.00 Yes BS GRS Yes Yes Yes Yes Yes 20 93ECSP-D EDG C ENGINE CONTROL SUB PANEL EG 272.00 27,A3 272.00 Yes BS GRS Yes Yes Yes Yes Yes I i i Certification: Certdication: All the mformation contained on this Screening Venficahon Data Sheet (SVDS)is, to the best of our The information provided to the Seismic Capabddy Engineers regard.ng systems and operations of , knowledge and belief, correct and accurate. 'All informatton' includes each entry and conclusion the equipment contained in the SVDS is, to the best of our knowledge and behef, correct and 1 (whether venfied to be seismically adequate or not). accurate. l Approved. (Segnatures of all Seismic Capabildy Engineers on the Seismic Review Team (SRT) are Approved: (One signature of Systems or Operations Engineer is required if the Seismic Capabildy required; there should be atleast two on the SRT, All signatories should agree with aR the entries Engineers deem it necessary ) and conclusions. One signatory should be a licensed sional engineer.) t l Pnit Okas l g7 /11 3 lh
'I Date Wl Pnnt or Type Name l
Signature l Date l Pnnt or Type Name " " E legnature i Steve Anagnostis F/Y[ [ Sg6ature l T[A /9$T
/ Dal6 Pnnt or Type Name l _
Signature l Date l Pnnt or Type Name f[ l l 1 I l l l Pnnt or Type Name Segnature Date Pnnt or Type Name Signature Date 1 1 _.- _m _,_
O O C JAMES A. FITZPATRICK NUCLEAR POWER PLANT Page 25/26 SCREENING VERIFICATION DATA SHEET (SVDS) Eq Eq ID Sys/Eq. Dese B4dg. Fi El. Rm or Base El. <40'? Cap. Demd. Cap > Caveats Anchor interact Equip Cl Rw/Cl Spec. Spec Demd? OK? OK? OK? OK7 7 02RV-71A ADS MAIN STEAM LINE A SAFETY / RELIEF VALVE PC 295.92 5R 278 00 Yes BS GRS Yes Yes N/A Yes Yes 7 02RV-71B ADS MAIN STEAM LINE A SAFETY / RELIEF VALVE PC 295.92 5R 278 00 Yes BS GRS Yes Yes N/A Yes Yes 7 02RV-71C ADS MAIN STEAM LINE B SAFETY / RELIEF VALVE PC 295.92 5R 278 00 Yes BS GRS Yes Yes N/A Yes Yes 7 02RV-71D ADS MAIN STEAM LINE B SAFETY / RELIEF VALVE PC 295.92 4.5 R 278 00 Yes BS GRS Yes Yes N/A Yes Yes 7 02RV-71E ADS MAIN STEAM LINE C $AFETY/ RELIEF VALVE PC 295.92 5W 278 00 Yes BS GRS Yes Yes N/A Yes Yes 7 02RV-71F ADS MAIN STEAM LINE C'BAFETY/ RELIEF VALVE PC 295.92 5W 278 00 Yes BS GRS Yes Yes N/A Yes Ps_ 7 02RV-71G ADS MAIN STEAM LINE C SAFETY / RELIEF VALVE PC 295.92 4.5 W 278 00 Yes BS GRS Yes Yes N/A Yes Yes 7 02RV-7181 ADS MAIN STEAM LINE D SAFETY / RELIEF VALVE PC 295 92 5W 278 00 Yes BS GRS Yes Yes N/A Yes Yes 7 02RV-71J ADS MAIN STEAM LINE D SAFETY / RELIEF VALVE PC 295.92 5W 278 00 Yes BS GRS Yes Yes N/A Yes Yes 7 02RV-71K ADS MAIN STEAM LINE A SAFETY / RELIEF VALVE PC 295.92 5.5 R 278.00 Yes BS GRS Yes Yes N/A Yes Yes 7 02RV-71L ADS MAIN STEAM LINE D SAFETY / RELIEF VALVE PC 295.92 5.5 W 278 00 Yes BS GRS Yes Yes N/A Yes Yes i 7 10AOV-68A RHR A LPCI TESTABLE CHECK VALVE PC 284.00 5R 278.00 Yes BS GRS Yes Yes N/A Yes Yes 7 10AOV488 RHR B LPCI TESTABLE CHECK VALVE PC 284.00 4.5 W 278.00 Yes BS GRS Yes Yes N/A Yes Yes 8 10MOV-17 RHR SHUTDOWN COOLING OUTBD ISOL VALVE RB 272.00 .3R 272.00 Yes BS GRS Yes Yes N/A Yes Yes 8 10MOV-18 RHR SHUTDOWN COOLING INBD ISOL VALVE PC 272.00 3T 278.00 Yes BS GRS Yes Yes N/A Yes Yes 8 10SOV-68A RHR A TESTABLE CHECK AIR SUPPLY ISOL SOLENOID VALVE PC 272.00 5R 278 00 Yes BS GRS Yes Yes N/A Yes Yes 8 10SOV488 RHR B TESTABLE CHECK AIR SUPPLY ISOL SOLENOID VALVE PC 272.00 4.5 W 278.00 Yes BS GRS Yes No N/A Yes No 7 10SV-44 REACTOR HEAD SPRAY LINE SAFETY VALVE RB 272.00 3W 272.00 Yes BS GRS Yes Yes N/A Yes Yes 8 12MOV-15 RWCU SUPPLY INBD ISOL VALVE PC 292 00 4T 278.00 Yes BS GRS Yes Yes N/A Yes Yes 8 13MOV-15 RCIC STEAM SUPPLY INBD ISOL VALVE PC 291.00 4R 278 00 Yes BS GRS Yes Yes N/A Yes Yes 8 13MOV-16 RCIC TURBINE STEAM SUPPLY OUTBD ISOL VALVE RB 274.00 3R 272 00 Yes BS GRS Yes Yes N/A Yes Yes 8 23MOV-15 HPCI STEAM SUPPLY INBD ISOL VALVE PC 269.75 4W 278 00 Yes BS GRS Yes Yes N/A Yes Yes 8 23MOV-60 HPCI TURBINE STEAM SUPPLY OUTBD ISOL VALVE 23MOV-16 RB 272.00 3W 272.00 Yes BS GRS Yes Yes N/A Yes Yes BYPASS VALVE 7 29AOV-80A MST A INBD MAIN STEAM ISOL VALVE PC 276 83 5.5 T 278 00 Yes BS GRS Yes Yes N/A Yes Yes t 7 29AOV-800 MST B INBD MAIN STEAM ISOL VALVE PC 276 83 5.5 T 278.00 Yes BS GRS Yes Yes N/A Yes Yes , 7 29AOV-80C MST C INBD MAIN STEAM ISOL VALVE PC 276 83 5.5 T 278 00 Yes BS GRS Yes Yes N/A Yes Yes Certification: Certification: As the informabon contained on this Screening Verificat on Data Sheet (SVDS) is, to the best of our The information provided to the Seismic Capabikty Engineers regarding systems and operations of knowledge and behef, correct and accurate. "All information" includes each entry and conclusion the equipment contained in the SVDS is, to the best of our knowledge and behef, correct and (whether venfied to be seismically adequate or not). accurate. t Approved: (Sgnatures of all Seismic Capabihty Engineers on the Seismic Review Team (SRT) are Approved: (One signature of Systems or Operations Engineer is required if the Seismic Capabihty required, there should be atleast two on the SRT. All signatories should agree with all the entries Engineers deem it necessary.) and conclusions. One signatory should be a licensed professi nal engineer.) l Walter Djordjevic l l [l l l l Pnnt or Type Name Sgna re Dati Pnnt or Type Name Sgnature Date l Steve Anagnostis l M-l X[/T/Ml l l l Pnnt or Type Name f/ Sgsdfure /Date/ Pnnt or Type Name Sgnature Date 1 I I l I I I Pnnt or Type Name Sgnature Date Pnnt or Type Name Signature Date _ _ _ _ . _ _ _ _ . _ _ _ _ _ . _ . . _ . _ _ _ _ _ . _ . _ . _ _ . _ . _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ___ ____ .= _ ._ __.
)
O \
%d JAMES A. FITZPATRICK NUCLEAR POWER PLANT Page 26/26 SCREENING VERIFICATION DATA SHEET (SVDS)
Eq Eq ID Sys/Eq. Desc Bldg. Fl EL Rm or Base Et (40*? Cap. Demd. Cap > Caveats Anchor interact Equip Cl Rw/Cl Spec. Spec Demd? OK7 OK? OK? OK7 7 29AOV-800 MST D INBD MAIN STEAM ISOL VALVE PC 276 83 5.5 T 278 00 Yes BS GRS Yes Yes N/A Yes Yes 7 29AOV-86A MST A OUTBD MAIN STEAM ISOL VALVE ST 276.67 6.5 T 278 00 Yes BS GRS Yes Yes N/A Yes Yes 7 29AOV-868 MST B OUTBD MAIN STEAM iSOL VALVE ST 280 00 6.5 T 278.00 Yes BS GRS Yes Yes N/A Yes Yes 7 29AOV-86C MST C OUTBD MAIN STEAtl ISOL VALVE ST 280 00 6.5 T 278 00 Yes BS GRS Yes Yes N/A Yes Yes 7 29AOV-860 MST D OUTBD MAIN STEAM ISOL VALVE ST 280 00 6.5 T 278 00 Yes BS GRS Yes Yes N/A Yes Yes
.3 h
Cert 6 cation. Certrhcation: As the information contained on thrs Screening Venfication Data Sheet (SVDS) is, to the best of our The information provided to the Seismic Capabihty Engineers regarding systems and operations of knowledge and belief, correct and accurate. "All information" includes each entry and conclusion the equipment contained in the SVDS is, to the best of our knowledge and be!ef, correct and (whether venfed to be seismically adequate or not). accurate. Approved. (Signatures of all Setsmic Capabihty Engineers on the Seismic Review Team (SRT) are Approved: (One signature of Systems or Operations Engineer is required if the Seismic Capabihty required, there should be atieast two on the SRT. All signatories should agree with all the entnes Engineers deem it necessary.) and conclusions. One signatory should be a hcensed profe io I engineer.) Walter Diordjevic l e l l l l l [ Pnnt or Type Name Sgnature Date Pnnt or Type Name Sg ture Dat6 l Steve Anagnostis l Die bl Pnnt or Type Name l Sgnature l Date l Pnnt or Type Name / / S(nature I I I I I l 1 Pnnt or Type Narr:e Sgnature Date Pnnt or Type Name S qnature Date
Cross Reference of EquipmentIDs and SCEs ID SCEs ID SCEs ID SCEs 1 02RV-71A WD SA 59 10MOV-27A AP SA 117 16-1 RTD-134B AP SA 2 02RV-718 WD SA 60 10MOV-278 AP SA 118 16-1RTD-135A AP SA 3 02RV-71C WD SA 61 10MOV-34A ML WD 119 16-1RTD-135B AP SA 4 02RV-71D WD SA 62 10MOV-34B ML WD 120 16-1RTD-136A AP SA 5 02RV-712 WD SA 63 j MOV-39A ML WD 121 16-1RTD-136B /sP SA
-6 02RV-71F WD SA 64 1 : AOV 39B ML WD 122 16-1RTD-137A AP SA 7 02RV-71G WD SA 65 I.a OV-66A ML WD 123 16-1 RTD-137B AP SA 8 02RV 71H WD SA 66 10MOV-66B ML WD 124 16-1RTD-138A AP SA 9 02RV-71J WD SA 67 10MOV-89A AP SA 125 16-1 RTD-138B AP SA 10 02RV-71K WD SA 68 10MOV-89B AP SA 126 16-1RTD 139A AP SA 11 02RV-71L WD SA 69 10P-1 A AP SA 127 16-1 RTD-139B AP SA 12 03AOV-126 ML WD 70 10P-1B AP SA 128 16-1 RTD-140A AP SA 13 03AOV-127 ML WD 71 10P-1C AP SA 129 16-1 RTD-140B AP SA 14 03AOV-32 AP SA 72 10P-1D AP SA 130 16-1 RTD-141 A AP SA 15 03AOV-35 AP SA 73 10P-3A ML WD 131 16-1RTD-141B AP SA 16 03AOV-34 AP SA 74 10P-3B ML WD 132 16-1 RTD-142A AP SA 17 03A OV-35 AP SA 75 10P-3C ML WD 133 16-1 RTD-142B AP SA 18 03AOV-36 AP SA 76 10P-3D ML WD 134 16-1 RTD-143A AP SA 19 03AOV-37 AP SA 77 10RV-41 A ML WD 135 16-1RTD-143B AP SA 20 03AOV-38 AP SA 78 10RV 41B ML WD 136 16-1RTD-144A AP SA 21 03AOV-39 AP SA 79 10RV-41C ML WD 137 16-1 RTD-144B AP SA 22 03SOV-117 ML WD 80 10RV-41D ML WD 138 16-1RTD-145A AP SA 23 03SOV-118 ML WD 81 10RV-43A AP SA 139 16-1RTD-145B AP SA 24 03SOV-140A ML WD 82 10RV43B AP SA 140 16-1RTD-146A AP SA 25 03SOV-140B ML WD 83 10RV-46A AP SA 141 16-1 RTD-146B AP SA 26 03SOV-31 A ML WD 84 10RV-46B AP SA 142 23AOV-42 AP SA 27 03SOV-31B ML WD 85 10SOV-101 A AP SA 143 23HOV-1 AP SA f 28 03TK-125 ML WD 86 10SOV-101B AP SA 144 23LT-202A AP SA
(}/ 29 03TK-128 30 09-21 ML WD AP SA 87 88 10SOV-101C 10SOV-101D AP SA AP SA 145 146 23LT-202B 23MOV-14 AP SA AP SA 31 09-3 AP SA 89 10SOV-68A WD SA 147 23MOV-15 WD SA 32 09-32 AP SA 90 10SOV-68B WD SA 148 23MOV-16 AP BK 33 09-33 AP SA 91 10SV-35A ML WD 149 23MOV-17 AP SA 34 09-39 AP SA 92 10SV-35B ML WD 150 23MOV-19 PO BK SA 35 09-45 AP SA 93 10SV-44 WD SA 151 23MOV-21 PO BK SA 36 09-46 AP SA 94 10SV-74A AP SA 152 23MOV-24 AP SA 37 09-47 AP SA 95 10SV-74B AP SA 153 23MOV-25 PO BK SA 38 09-5 AP SA 96 11 EV-14A ML WD 154 23MOV-57 AP SA 39 09-6 AP SA 97 11 EV-14B ML WD 155 23MOV-58 F0 BK SA 40 09-95 AP SA 98 11 P-2A ML WD 156 23MOV-60 WD SA 41 09-96 AP SA 99 11P-2B ML WD 157 23P-150 AP SA 42 09AR-5A AP SA 100 11SV-39A ML WD 158 23P-1 M AP SA 43 09AR-5B AP SA 101 11SV-398 ML WD 159 23RV-106 AP SA 44 10AOV-68A WD SA 102 12MOV-15 WD SA 160 23RV 107 AP SA 45 10AOV-688 WD SA 103 12MOV-18 ML WD 161 23SV-34 AP SA 46 10DPIS-125A AP SA 104 13MOV-15 WD SA 162 23SV-66 AP SA 47 10DPIS-125B AP SA 105 13MOV 16 WD SA 163 23TU-2 AP SA 48 10FT-109B ML WD 106 15PS-122A AP SA 164 25-01 ML WD 49 10MOV-15A ML WD 107 15PS-122B AP SA 165 25-05 ML WD 50 10MOV-15B ML WD 108 15PS-122C AP SA 166 25-06 ML WD 51 10MOV-15C ML WD 109 15PS-122D AP SA 167 25-50 ML WD 52 10MOV-15D ML WD 110 16-1 RTD-131 A AP SA 168 25-59 ML WD 53 10MOV-16A ML WD 111 16-1 RTD-131B AP SA 169 25-60 ML WD 54 10MOV-16B ML WD 112 16-1RTD-132A AP SA 170 25-62 ML WD 55 10MOV-17 WD SA 113 16-1RTD-132B AP SA 171 27AOV-126A PO ML SA 56 10MOV-18 WD SA 114 16-1RTD-133A AP SA 172 27AOV 126B PO ML SA 57 10MOV-25A AP SA 115 16-1RTD-133B AP SA 173 27AOV-127A PO ML SA 58 10MOV-25B AP SA 116 16-1RTD-134A AP SA 174 27AOV-127B PO ML SA l JAFNPP A-46 Seismic Evaluation Report September 1995 Appendix B
( ID SCEs ID SCEs ID SCEs 175 27AOV 128A PO ML SA 235 66UC-22G ML WD 295 71BMCC-1 AP SA (/ 176 177 27AOV-129A 27AOV-131 A PO ML SA PO BK SA 236 237 66UC-22H 66UC-22J ML WD ML WD 296 297 71BMCC-2 71BMCC-3 AP SA AP SA 178 27AOV-1318 PO BK SA 238 66UC-22K ML WD 298 71BMCC-4 AP SA 179 27AOV-132A PO BK SA 239 67E-11 ML WD 299 71BMCC-6 AP SA 180 27AOV-1328 PO BK SA 240 67E-14 ML WD 300 71DC-A2 AP SA 181 27 CAD AP SA 241 67PCV-101 ML WD 301 71 DC-A4 AP SA 182 27EH-10A PO ML SA 242 67UC-16A ML WD 302 71DC-A5 AP SA 183 27EH-108 PO ML SA 243 67UC-16B ML WD 303 71DC-82 AP SA 184 27 MAP AP SA 244 70AHU-12A ML WD 304 71DC-84 PO SA 185 27NS-CA PO ML SA 245 70AHU-128 ML WD 305 71DSC-11561 AP SA 186 27NS-CB PO ML SA 246 70AHU-19A ML WD 306 71DSC-11661 PO SA 187 27PCV-116A AP SA 247 70AHU-19B ML WD 307 71DSC-12561 AP SA 188 27PCV-1168 AP SA 248 70AHU-3A ML WD 308 71DSC-12661 PO SA 189 27PCV-122A PO ML SA 249 70AHU-3B ML WD 309 71 ESSA 1 AP SA 190 27PCV-122B PO ML SA 250 70FD-1 ML WD 310 71ESSB1 AP SA 191 27PCV-134A PO ML SA 251 70FD-10 ML WD 311 71H05 AP SA 192 27PCV-1348 PO ML SA 252 70FD-2 ML WD 312 71H06 PO SA 193 27PCV-140 PO ML SA 253 70FD-4 ML WD 313 711NV-3A AP SA 194 27PT-115A2 AP SA 254 70FD-5 ML WD 314 711NV-3B AP SA 195 27PT-115B2 AP SA 255 70FD-6 ML WD 315 71L15 AP SA i 196 27RV-101 A PO ML SA 256 70FD-7 ML WD 316 71L16 AP SA ] 197 27RV-101B PO ML SA 257 70FN-13A ML WD 317 71L25 AP SA 198 27SV-114A PO ML SA 258 70FN-13B ML WD 318 71L26 AP SA 199 27SV-1148 PO ML SA 259 70FN-4A ML WD 319 71MCC-151 AP SA 200 27SV-115A PO ML SA 260 70FN-4B ML WD 320 71MCC-152 AP SA ) 201 27SV-115B PO ML SA 261 70 MOD-101 A ML WD 321 71MCC-153 AP SA 202 27SV-118A PO ML SA 262 70 MOD 101B ML WD 322 71MCC-155 AP SA 203 27SV-1188 PO ML SA 263 70 MOD-102A ML WD 323 71MCC-156 AP SA 204 27SV-119A PO ML SA 264 70 MOD-102B ML WD 324 71MCC-161 AP SA O 205 206 207 27SV-119B 27SV-121 27SV-122 PO ML SA PO ML SA PO ML SA 265 266 267 70 MOD-104A 70 MOD-104B 70 MOD-106A ML WD ML WD ML WD 325 326 327 71MCC-162 71MCC-163 71MCC-165 AP SA AP SA AP SA l 208 27SV-201A PO ML SA 268 70 MOD-1068 ML WD 328 71MCC-166 AP SA l l 209 27SV-201B PO ML SA 269 70 MOD-108A ML WD 329 71MCC-251 AP SA 210 27SV-202 PO ML SA 270 70 MOD-108B ML WD 330 71MCC-252 AP SA 211 29AOV-80A WD SA 271 70 MOD-110A ML WD 331 71MCC-253 ML WD 212 29AOV-80B WD SA 272 70 MOD-110B ML WD 332 71MCC-254 AP SA 213 29AOV-80C WD SA 273 70PCV-100A1 ML WD 333 71MCC-261 AP SA 214 29AOV-80D WD SA 274 70PCV-100A2 ML WD 334 71MCC-262 AP SA 215 29AOV-86A WD SA 275 70PCV-100B1 ML WD 335 71MCC-263 AP SA 216 29AOV-86B WD SA 276 70PCV-10082 ML WD 336 71MCC-264 AP SA 217 29AOV-86C WD SA 277 70RV-101 A ML WD 337 71PT-71 ACA2 AP SA 218 29AOV-86D WD SA 278 70RV-101 B ML WD 338 71PT-71 ACA4 AP SA 219 33LT-101 PO SA 279 70RWC-2A(CND) ML WD 339 71PT-71 ACB2 AP SA 220 46MOV-101 A AP SA 280 70RWC-2B(CND) ML WD 340 71PT-71 ACB4 AP SA 221 46MOV-101B AP SA 281 70TCV-123A ML WD 341 71PT-71 ACUPS PO DH 222 46MOV-102A AP SA 282 70TGV 123E ML WD 342 71PT-71 ESSA 1 AP SA 223 46MOV-1028 AP SA 283 71ACA2 ML WD 343 71PT-71ESSB1 ML WD 224 46P-2A AP SA 284 71ACA4 AP SA 344 71SB-1 ML WD 225 46P-2B AP SA 285 71ACB2 AP SA 345 71SB-2 ML WD 226 66PCV-101 ML WD 286 71ACB4 AP SA 346 71T-13 AP SA 227 66TCV-107E ML WD 287 71ACUPS PO DH 347 71T-14 PO SA 228 66TCV-107F ML WD 288 71 ACUPS-1 PO DH 348 71T-15 PO SA 229 66UC-22A ML WD 289 71 BAT-3A ML WD 349 71T-16 AP SA 230 66UC-22B ML WD 290 71 BAT-3B ML WD 350 71UPP PO DH 231 66UC-22C ML WD 291 71BC-1 A ML WD 351 71UPS 1 PO DH 232 66UC-22D ML WD 292 71 BC-1B ML WD 352 72AHU-30A ML WD 233 66UC-22E ML WD 293 71 BCB-2A ML WD 353 72AHU-30B ML WD 234 %UC-22F ML WD 294 71 BCB-2B ML WD 354 72FD-13 ML WD JAFNPP A-46 Seismic Evaluation Report September 1995 Appendix B
_ _ _ _ - _ . _ . . _ _ _ . _ _ _ _. . _ . _ ..__._ _ ._ _ m j s ID SCEs ID SCEs ) 355 72FD-14 ML WD 415 92RTD-101D PO SA k 356 72FD-3 ML WD 416 93AURP-01 AP SA 357 72FD-4 ML WD 417 93AURP-02 PO SA 358 72FD-5 ML WD 418 93ECP-A AP SA 359 72FD-6 ML WD 419 93ECP-B PO SA 360 72FN-31A ML WD 420 93ECP-C AP SA i 361 72FN-318 ML WD 421 93ECP-D PO SA 362 72FN46A ML WD 422 93ECSP-A AP SA 363 72FN-468 ML WD 423 93ECSP-B PO SA 364 72FN-46C ML WD 424 93ECSP-C AP SA 365 72FN-46D ML WD 425 93ECSP-D PO SA l 366 72 MOD-102A ML WD 426 93EDG-A AP SA 367 72 MOD-102B MtWD 427 93EDG-B PO SA
- 368 72 MOD-104A ML WD 428 93EDG-C AP SA
^ 369 72 MOD-104B ML WD 429 93EDG-D PO SA 370 73FD-1A AP SA 430 93EGP-A AP SA 371 73FD-18 AP SA 431 93EGP-B PO SA 372 73FD-1C AP SA 432 93EGP-C AP SA 373 73FD-1D AP SA 433 93EGP-D PO SA
' 374 73FN-3A AP SA 434 93FPAC AP SA 375 73FN-3B AP SA 435 93FPBD PO SA I 376 92CD-1 PO SA 436 93P1-A1 AP SA l 377 92CD-2 PO SA 437 93P1-A2 AP SA 378 92CD-3 PO SA 438 93P1-B1 PO SA
)
j ! 379 92CD-4 PO SA 439 93P1-B2 PO SA i l 380 92FD-1 AP SA 440 93P1-C1 AP SA 381 92FD-10 PO SA 441 93P1-C2 AP SA ] 382 92FD-2 AP SA _442 93P1-01 PO SA 383 92FD-3 AP SA 443 93P1-D2 PO SA 384 92FD-4 AP SA
,i g 385 92FD-5 AP SA 386 92FD-6 PO SA 387 92FD-7 PO SA 388 92FD-8 PO SA 389 92FD-9 PO SA 390 92F N-1 A PO SA 391 92FN-1B PO SA 392 92FN-1C PO SA 393 92FN-1D PO SA 394 92HV-9A PO SA 395 92HV-98 PO SA 396 92 MOD-143A AP SA l 397 92 MOD-143B PO SA l 398 92 MOD-143C AP SA 399 92 MOD-143D PO SA 400 92 MOD-148A AP SA J 401 92 MOD-148B PO SA 402 92 MOD-148C AP SA 400 92 MOD-148D PO SA 404 92 MOD-149A AP SA 405 92 MOD-149B PO SA 406 92 MOD-149C AP SA 407 92 MOD-149D PO SA 408 92 MOD-150A AP SA 409 92 MOD-150B PO SA 410 92 MOD-150C AP SA 411 92 MOD-150D PO SA 412 92RTD-101 A PO SA 413 92RTD-101 B PO SA 414 92RTD-101C PO SA _
JAFNPP A-46 Seismic Evaluation Report September 1995 Appendix B
l p, Appendix C - Plant Area Summary Sheets (PASS) ; , L) l This appendix contains the Plant Area Summary Sheets (PASS). A list of the PASS and the plant areas they cover is provided below, l PASS # Plant Area i RACE 001 East and West Crescents RACE 002 Torus RACE 003 Reactor Building 272 RACE 004 Reactor Building 300 RACE 005 Reactor Building 326 RACE 006 Reactor Building 344 RACE 007 Cable Tunnels 260 4 RACE 006 Cable Tunnels 286 RACE 009 Electrical Bay RACE 010 Emergency Diesel Generator Area RACE 011 Service Water Pump Area RACE 012 Battery Rooms
/]
RACE 013 Cable Spreading Room RACE 014 Relay Room RACE 015 Control Room RACE 016 Control Room A/C Area RACE 017 CAD Building RACE 018 Drywell and Main Steam Tunnel f% J i l JAFNPP A-46 Seismic Evaluation Report September 1995 Appendix C
l
-I N2w Ycrk Pswer Auth:rity - FitzPItrick Nuciscr Pcw:r Plint GIP Rev 2, 2/14/92 Ca'alo and Conduit Raceway Review Shtst 1 of 4 Plant Area Summary Sheet 10 : RACE 001 (Rev. 0) Plant Area : East and West Crescents i
(' Building : RB Floor El. : 227.00 l Room, Row / Col - ! l Check List inclusion Rule Review Acceptance '
- 1. Cable Tray Span Yes
- 2. Conduit Span Yes
- 3. Tie Downs Yes
- 4. Channel Nuts Yes
- 5. Rigid Boots N/A i
- 6. Beam Clamps Yes I
- 7. Cast iron inserts N/A Other Seismic Performance Concem Review Acceptance 1
- 1. Anchorage Yes
- 2. Welded Connections Yes
- 3. Concrete Condition Yes
- 4. Corrosion N/A
- 5. Sagging Raceways N/A
- 6. Broken or Missing Components and Sharp Edges N/A
- 7. Restraint of Cables N/A
- 8. Cable Fill / Ties N/A
- 9. Aging of Plastic Ties N/A
,/] __ (j 10. System Hardspots N/A
- 11. Short Rods N/A Seismic Interaction Review Acceptance
- 1. Proximate Features Yes
- 2. Falling Hazards Yes
- 3. Differential Displacement Yes
- 4. Isolated Outliers Yes
-e 2
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i N:w Ycrk Psw:r Auth::rity - FitzPItrick Nucl=r Powsr PI:nt GlP Rsv 2, 2/14/92 i Cable and Conduit Raceway Review Shsst 2 of 4 Plant Area Summary Sheet I
/ -
ID : RACE 001 (Rev. O) Plant Area : East and West Crescents I U Building : RB Floor El. 227.00 l Room, Row / Col : COMMENTS ] SRT: Arun Pal (NYPA), Steve Anagnostis (S&A)- week of 9/19/94. PLANT AREA: East and West Reactor Building Crescents, Elevation 227 up to 272. l TRAY TYPE: 4" deep PW Industries ladder tray; up to 24" wide. TRAY FILL: up to 100%, typically less TRAY SPANS: 6' to 8' CONDUlT SIZES: up to 4" CONDUlT SPANS: less than GIP allowables TYPICAL SUPPORTS: j
- 1. Rigid welded steel wall brackets anchored to r/c walls with shell anchors, spaced at 6'-8', supporting up to four j (4) 24" trays. i
- 2. 3/4" threaded rod trapeze hangers bearn clamped to building steel, spaced at 6'- 8', supporting up to three (3) ;
24" trays. l l
- 3. Conduit rigidly mounted to r/c walls.
LAR: Type i support (see atta hed field sketch). p} l t - - Evaluated by: /V' Date: {/c? 8/ 9F f ( " f T O
/ 6
Attachment:
Pictures
Attachment:
Field Sketch
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New York Power Authority - FitzPatrick Nuclear Power Plant GIP Rev 2, 2/14/92 Cable and Conduit Raceway Raview Sheet 3 of 4 Plant Area Summary Sheet ID : RACE 001 (Rev. 0) Plant Area : East and West Crescents Building : R8 Floor El. 227.00 l Room, Row / Col : PICTURES
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N;w Yerk Pewsr Auth:rity - FitzPr. trick Nucl: r Powsr PI:nt GlP Rsv 2, 2/14/92 Cable and Conduit Raceway Review Shsst 4 of 4 Plant Area Summary Sheet ID : RACE 001 (Rev. 0) Plant Area : East and West Crescents [V) Building : RB Floor El. : 227.00 l Room, Row / Col - Elf.1d Sketch e I l f, :'- . . _ _ 7 l I&
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I NIw Ycrk Pawar Auth:rity - FitzPitrick Nucistr Pcw;r PI:nt GIP Rsv 2, 2/14/92 Cable and Conduit R;cswty R:vitw Shsst 1 of 2 Plant Area Summary Sheet ID : RACE 002 (Rev. 0) Plant Area : Torus
- v. / Building SU Floor El. : 227.00 l Room, Row / Col :
Check List inclusion Rule Review Acceptance
- 1. Cable Tray Span Yes
- 2. Conduit Span Yes
- 3. Tie Downs Yes
- 4. Channel Nuts Yes
- 5. Rigid Boots N/A
- 6. Besrn Clamps Yes
- 7. Cast Iron Inserts N/A Other Seismic Performance Concern Review Acceptance
- 1. Anchorage Yes
- 2. Welded Connections N/A 4
- 3. Concrete Condition Yes
- 4. Corrosion N/A
- 5. Sagging Raceways N/A
- 6. Broken or Missing Components and Sharp Edges N/A
- 7. Restraint of Cables Yes ,
- 8. Cable Fill / Ties Yes !
- 9. Aging of Plastic Ties Yes Yes (j 10. System Hardspots Yes
- 11. Short Rods Seismic Interaction Review Acceptance
- 1. Proximate Features Yes
- 2. Falling Hazards Yes
- 3. Differential Displacement Yes
- 4. Isolated Outliers Yes
- e
I Niw Ycrk Paw:r Authsrity - FitzP2 trick Nucl2rr Power Plint GIP Rav 2, 2/14/92 Cable and Conduit Raceway Review Shset 2 of 2 Plant Area Summary Sheet [ ID : RACE 002 (Rev. 0) Plant Area : Torus V Building : SU Floor El. : 227.00 l Room, Row / Col COMMENTS SRT: Arun Pal (NYPA), Steve Anagnostis (S&A)- 9/12/94 PLANT AREA: Torus compartment, all elevations. TRAY TYPE: 4" deep PW Industries ladder tray; up to 24" wide. TRAY FILL: <= 50% TRAY SPANS: < 10' j 1 CONDUlT SIZES: up to 4" CONDUlT SPANS: <10',6' to 8' typical. l TYPICAL SUPPORTS: l
- 1. 5/8" threaded rod trapeze hangers anchored by;
- a. bolted into embedded strut i
- b. expansion anchors
- c. beam clamps to building steel Hangers up to 6' tall, support up to 4 trays, and are typically spaced at -8'. j
- 2. Conduit rifidly anchored to r/c walls, floor, ceiling.
( LAR: None, covered by LARs from other areas. -v/ Evaluated by: Date: / ) b D- ) g 7 iV l l OT U .
N&w Ycrk Pawsr Auth:rity - FitzP: trick Nucircr Power Plant GIP Rav 2, 2/14/92 Cebin cnd Ccnduit Rac wsy Rsvisw Sheet 1 of 3 Plant Area Summary Sheet ! O V ID : RACE 003 (Rev. 0) Building : RB Plant Area : Reactor Building 272 Floor El. : 272.00 l Room, Row / Col : Checklist inclusion Rule Review Acceptance
- 1. Cable Tray Span Yes
- 2. Conduit Span Yes j
- 3. Tie Downs Yes l
- 4. Channel Nuts Yes j
- 5. Rigid Boots N/A
- 6. Beam Clamps Yes !
- 7. Cast iron Inserts N/A i l
)
Other Seismic Performance Concern Review Acceptance
- 1. Anchorage Yes
- 2. Welded Connections N/A
- 3. Concrete Condition Yes 1
- 4. Corrosion N/A
- 5. Sagging Raceways N/A
- 6. Broken or Missing Components and Sharp Edges N/A
- 7. Restraint of Cables Yes l
- 8. Cable Fill / Ties Yes I
- 9. Aging of Plastic Ties Yes
- 10. System Hardspots N/A
- 11. Short Rods N/A Seismic Interaction Review Acceptance
- 1. Proximate Features Yes
- 2. Falling Hazards Yes
- 3. Differential Displacement Yes
- 4. Isolated Outliers Yes
Nsw Ycrit Pawar Auth rity - FitzP trick Nuclur Powtr Plant GIP Rav 2, 2/14/92 Cable and Conduit Raceway Review Shsst 2 of 3 Plant Area Summary Sheet
/ ID : RACE 003 (Rev. 0) Plant Area : Reactor Building 272 5-- Building : RB Floor El. 272.00 l Roorn, Row / Col :
COMMENTS SRT: Arun Pal (NYPA), Steve Anagnostis (S&A)- week of 9/19/94. PLANT AREA: Reactor Building Elevation 272. TRAY TYPE: 4" deep PW Industries ladder tray; up to 24" wide. TRAY FILL: up to 100%, typically less TRAY SPANS: 6' to 8' CONDUlT SIZES: up to 4" CONDUlT SPANS: less than GIP allowables TYPICAL SUPPORTS:
- 1. 3/4" threaded rod trapeze hangers anchored by:
- a. 3/4" shells (Phillips self-drill)
- b. embedded strut
- c. bolted to P1000 spanning between embedded struts Hangers are up to 15' tall, support up to seven (7) 24" trays, and are spaced at 6' to 8'.
- 2. Conduit rigidly anchored to r/c walls, floors, and ceilings.
s 3. Conduit on lightly loaded rod trapeze hangers. 1 LAR: Type 1 support (see attached field sketch). Evaluated by: / (___ Date: 8 Y9F
/ / 3
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Attachment:
Field Sketch
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3 j [ Nsw Ycrk Powsr Authcrity - FitzP: trick Nuciarr Powzr Pirnt GIP Rev 2, 2/14/92 Cable and Conduit Raceway Review Shest 3 of 3
- Plant Area Summary Sheet
[ ID : RACE 003 (Rev. 0) Plant Area : Reactor Building 272 Building RB Floor El. : 272.00 l Room, Row / Col : i 2 Field Sketch l ., ( [- W- -l I l at l i' mea * '- 1/o Sow i ubh !
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Nsw Ycrk P:wnr Auth:rity - FitzP; trick Nucl=r Pewsr.PI:nt GIP Rav 2, 2/14/92 Cable and Conduit Raceway Review Shast 1 of 2 Plant Area Summary Sheet 7 ID : RACE 004 (Rev. 0) Plant Area : Reactor Building 300 'v) ( Building : RB Floor El. 300.00 l Room, Row / Col - Check List inclusion Rule Review Acceptance
- 1. Cable Tray Span Yes
- 2. Conduit Span Yes
- 3. Tie Downs Yes
- 4. Channel Nuts Yes
- 5. Rigid Boots N/A O. Beam Clamps Yes
- 7. Cast Iron Inserts N/A l
Other Seismic Performance Concern Review Acceptance
- 1. Anchorage Yes
- 2. Welded Connections N/A
- 3. Concrete Condition Yes
- 4. Corrosion N/A
- 5. Sagging Raceways N/A
- 6. Broken or Missing Components and Sharp Edges N/A ,
- 7. Restraint of Cables Yes l
- 8. Cable Fill / Ties Yes l
- 9. Aging of Plastic Ties Yes
[] v 10. System Hardspots N/A
)
- 11. Short Rods N/A Seismic Interaction Review Acceptance
- 1. Proximate Features Yes
- 2. Falling Hazards Yes
- 3. Differential Displacement Yes
- 4. Isolated Outliers Yes
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N:w York P wIr Auth:rity - FitzP: trick Nuclear P wxr PI:nt GIP Rav 2, 2/14/92 Cabl3 cnd C:nduit R cowry R:vi:w Shest 2 of 2 Plant Area Summary Sheet / ID : RACE 004 (Rev. 0) Plant Area : Reactor Building 300 (O_) Building : RB Floor El. : 300.00 l Room, Row / Col : COMMENTS SRT: Arun Pal (NYPA), Steve Anagnostis (3&A)-week of 9/19/94. PLANT AREA: Reactor Building Elevation 300 TRAY TYPE: 4" deep PW Industries ladder tray; up to 24" wide. TRAY FILL: up to 100%, typically less TRAY SPANS: 6' to 8' CONDUIT SIZES: up to 4" CONDUlT SPANS: less than GIP allowables TYPICAL SUPPORTS:
- 1. 3/4" threaded rod trapeze hangers anchored by:
- a. directly bolted into embedded strut
- b. 3/4" shells (rare)
- c. bolted to P1000 spanning between embedded struts Hangers are up to 15' tall, support up to five 24" trays, and are spaced at 8'.
- 2. Conduit rigidly anchored to r/c walls, floors, and ceilings.
n LAR: None, covered by LARs from other areas. Evaluated by: Date: T/J'/73 ( V
N;w York PcwIr Auth:rity - FitzPatrick Nuciscr Pswsr Pirnt GIP Rav 2, 2/14/92 Cable and Conduit Raceway Review Shsst 1 of 3 Plant Area Summary Sheet O ID : RACE 005 (Rev. 0) Plant Area : Reector Building 326 Building : RB Floor El. : 326.00 l Room, Row / Col : Check List inclusion Rule Review Acceptance
- 1. Cable Tray Span Yes
- 2. Conduit Span Yes
- 3. Tie Downs N/A
- 4. Channel Nuts N/A
- 5. Rigid Boots N/A
- 6. Beam Clamps N/A
- 7. Cast Iron Inserts N/A Other Seismic Performance Concem Review Acceptance
- 1. Anchorage Yes
- 2. Welded Connections N/A
- 3. Concrete Condition Yes
- 4. Corrosion N/A
- 5. Sagging Raceways N/A
- 6. Broken or Missing Components and Sharp Edges N/A
- 7. Restraint of Cables N/A
- 8. Cable Fill / Ties N/A
(]j
- 9. Aging of Plastic Ties
- 10. System Hardspots
- 11. Short Rods Yes N/A N/A Seismic Interaction Review Acceptance
- 1. Proximate Features Yes
- 2. Falling Hazards N/A
- 3. Differential Displacement Yes !
- 4. Isolated Outliers N/A l
- - l O !
NIw Ycrk Pawsr Auth::rity - FitzPctrick Nucinr Pawsr Pl:nt GIP Rav 2, 2/14/92 Cable and Conduit Raceway Review Shsst 2 of 3
,s Plant Area Summary Sheet
[Oi ID : RACEOO5 (Rev. 0) Building : RB Plant Area : Reactor Building 326 Floor El. : 326.00 l Room, Row / Col * , COMMENTS I SRT: Arun Pal (NYPA), Steve Anagnostis (S&A)- 4/15/94. PLANT AREA: Reactor Building Elevation 326
)
TRAY TYPE: 4" deep PW Industries ladder tray; up to 24" wide. TRAY FILL: 25% or less TRAY SPANS: < 8' CONDUIT SIZES: up to 4" CONDUlT SPANS: < 10' TYPICAL SUPPORTS:
- 1. 3/4" threaded rod trapeze hangers anchored by: ,
- a. directly bolted into embedded strut
- b. bolted to P1000 spanning between embedded . ruts Hangers are up to 10' tall, support up to four 24" trayw and are spaced at <8'. j
- 2. Conduit rigidly anchored to r/c walls, floori, and ceilings. ;
LAR: None, covered by LARs from other areas. ( Evaluated by: [ -
' ~
Date: 8/A i/C
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Attachment:
Pictures
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1 l I New York Power Authority - FitzPatrick Nuclear Power Plant GIP Rev 2, 2/14/92 l
; Cable and Conduit Raceway Review Sheet 3 of 3 i Plant Area Summary Sheet ID : RACE 005 (Rev. 0) Plant Area : Reactor Building 326 Building : RB Floor El. : 326.00 l Room, Row / Col PlcTURES l
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N;w Ycrk Pswsr Auth::rity - FitzP; trick Nucinr Powcr PI:nt GIP Rev 2, 2/14/92 Cable and Conduit Raceway Review Shut 1 of 3 Plant Area Summary Sheet ID : RACE 006 (Rev. O) Plant Area : Reactor Building 344 Building : RB Floor El. : 344.00 l Room, Row / Col ; Check List inclusion Rule Review Acceptance
- 1. Cable Tray Span Yes
- 2. Conduit Span Yes
- 3. Tie Downs N/A
- 4. Channel Nuts N/A
- 5. Rigid Boots N/A
- 6. Beam Clamps N/A
- 7. Cast iron Inserts N/A Other Seismic Performance Concern Review Acceptance
- 1. Anchorage Yes
- 2. Welded Connections Yes
- 3. Concrete Condition Yes
- 4. Corrosion N/A
- 5. Sagging Raceways N/A
- 6. Broken or Missing Components and Sharp Edges N/A
- 7. Restraint of Cables N/A
- 8. Cable Fill / Ties N/A p
\,j
- 9. Aging of Plastic Ties
- 10. System Hardspots Yes N/A
- 11. Short Rods N/A Seismic Interaction Review Acceptance
- 1. Proximate Features Yes
- 2. Falling Hazards Yes
- 3. Differential Displacement Yes
- 4. Isolated Outliers Yes p.
O
NIw Ycrk P w:r Auth:rity - FitzP: trick Nucicar Pow:r PI:nt GlP Rev 2, 2/14/92 Cable and Conduit Raceway Review Shest 2 of 3 Plant Area Summary Sheet , ID : RACE 006 (Rev. O) Plant Area : Reactor Building 344 l v Building : RB Floor El. 344.00 l Room, Row / Col : l COMMENTS SRT: Arun Pal (NYPA), Steve Anagnostis (S&A)-4/15/94. PLANT AREA: Reactor Building Elevation 344 TRAY TYPE: 4" deep PW. Industries ladder tray; up to 24" wide. TRAY FILL: <25%, many close to empty. TRAY SPANS: 7' to 9' CC,WDUlT SIZES: up to 4" CONDUlT SPANS: < 10',6' to 8' typical
- TYPICAL SUPPORTS
- 1. 5/8" threaded rod trapeze hangers anchored by:
- a. directly bolted into embedded strut ,
- b. bolted to P1000 spanning between embedded struts l Hangers are up to 6' tall, support up to three 24" trays, and are typically spaced.at 7'.
2.1/2" and 5/8" threaded rod trapeze, same anchorage details as (1), supporting a few conduit on one tier. Heights up to 10', spacing <= 10'. 1 l
- 3. Conduit rigidly anchored to r/c walls, floors, and ceilings. j
- 4. One short run of "new" welded steel trapeze hangers anchored with substantial base plates and expansion l anchors. They're about 6' tall, spaced at 6', and support 2 trays that are essentially empty. j LAR: None, covered by LARs from other areas.
Evaluated by: f
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Attachment:
Pictures c-O ,
i New York Power Authority - FitzPatrick Nuclear Power Plant GlpRev 2, 2/14/92 Cable and Conduit Raceway Review Sheet 3 of 3 Plant Area Summary Sheet O ID : RACEOO6 (Rev. 0) Building : RB Plant Area : Reactor Building 344 Floor El. 344.00 l Room, Row / Col : PICTURES
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N:;w Ycrk ?sw r Auth:rity - FitzPatrick Nucirr P:w .r Pl:nt GlP Rav 2, 2/14/92 ] Cable and Conduit Raceway Review Shsst 1 of 5 Plant Area Summary Sheet - [, ID : RACE 007 (Rev. 0) Plant Area : Cable Tunnels 260 Y Building : CT Floor El.
- 260.00 l Room, Row / Col :
Check List inclusion Rule Review Acceptance
- 1. Cable Tray Span Yes
- 2. Conduit Span Yes
- 3. Tie Downs N/A
- 4. Channel Nuts Yes
- 5. Rigid Boots N/A
- 6. Beam Clamps N/A
- 7. Cast Iron Inserts N/A 1
Other Seismic Performance Concern Review Acceptance l
- 1. Anchorage Yes
- 2. Welded Connections N/A
- 3. Concrete Condition Yes
- 4. Corrosion N/A
- 5. Sagging Raceways N/A
- 6. Broken or Missing Components and Sharp Edges N/A I N/A !
- 7. Restraint of Cables
- 8. Cable Fill / Ties N/A
/7 9. Aging of Plastic Ties N/A ) h 10. System Hardspots
- 11. Short Rods N/A N/A Seismic Interaction Review Acceptance
- 1. Proximate Features N/A
- 2. Falling Hazards N/A
- 3. Differential Displacernent N/A
- 4. Isolated Outliers N/A
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NIw Ycrk Powtr Authsrity - FitzP: trick Nuciscr Psw r PI:nt GIP Rav 2, 2/14/92 Cable and Conduit Raceway Review Shost 2 of 5 , Plant Area Summary Sheet - ID : RACE 007 (Rev. 0) Plant Area : Cable Tunnels 260 Building : CT Floor El. : 260.00 l Room, Row / Col : COMMENTS SRT: Arun Pal (NYPA), Steve Anagnostis (S&A)- week of 9/19/94 PLANT AREA: Cable tunnels on El 260. , TRAY TYPE: 4" deep PW Industries ladder tray; 30* wide TRAY FILL: 0% - 100%, majority < 50%. TRAY SPANS: 6' to 8' CONDUlT SIZES: 2" to 6" CONDUlT SPANS: < GIP allowables TYPICAL SUPPORTS:
- 1. 3/4" threaded rod trapeze hangers anchored by:
- a. directly bolted into embedded strut
- b. Phillips self-drill shell anchors (less common)
Hangers are up to 8' tall, support up to six 30" trays, and are typically spaced at 6' to 8*.
- 2. Same as (12) except one end of each cross-piece is bolted to an embedded strut in an r/c wall rather than !
being supported by a rod.
- 3. Smaller conduit trapezes and conduit rigidly mounted conduit.
LAR: Type 1 support and Ty 2 support (see attached field sketch). Evaluated by:. Date: 72Pc /7
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Attachment:
Pictures
Attachment:
Field Sketch l v ,
New York Power Authority - FitzPatrick Nuclear Power Plant GIP Rev 2, 2/14/92 Cable and Conduit Raceway Review Sheet 3 of 5 Plant Area Summary Sheet l O 10 : RACE 007 (Rev. 0) Building : CT Plant Area : Cable Tunnels 260 Floor El. 260.00 l Room, Row / Col : l PICTURES i 1 l . 'l y . ~
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i 1 N;w Ycrk Psw;r Auth rity - FitzP: trick Nucinr Pcw:r Plint GIP Rsv 2, 2/14/92 , Cable and Conduit Raceway Review Sheet 4 of 5 I Plant Area Summary Sheet 4 10 : RACE 007 (Rev. 0) Plant Area : Cable Tunnels 260 'd Building : CT Floor El. ; 260.00 l Room, Row / Col : _ Field Sketch l lf/1 V6VP Lh3O D 6D[w i.es r. unM" l ott M ~3/9' TH ILctD SM 8
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Plant Area Summary Sheet l ID : RACE 007 (Rev. O) Plant Area : Cable Tunnels 260 O- Building : CT Floor El. : 260.00 l Room, Row / Col : i I
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N;;w York Powtr Authtrity - FitzP: trick Nuciser Power Pirnt GIP Rev 2, 2/14/92 j Cable and Conduit Raceway Review Shset 1 of 3 Plant Area Summary Sheet
.( ID : RACE 008 (Rev. 0) Plant Area : Cable Tunnels 286 Building : CT Floor El. : 286.00 l Room, Row / Col :
Check List inclusion Rule Review Acceptance
- 1. Cable Tray Span Yes
. 2. Conduit Span Yes l 3. Tie Downs N/A l 4. Channel Nuts Yes
- 5. Rigid Boots N/A
- 6. Beam Clamps Yes
- 7. Cast iron Inserts N/A l
Other Seismic Performance Concern Review Acceptance -l 1. Anchorage Yes j 2. Welded Connections N/A
- 3. Concrete Condition Yes a 4. Corrosion N/A
- 5. Sagging Raceways N/A
- 6. Broken or Missing Components and Sharp Edges N/A A
- 7. Restraint of Cables Yes
- 8. Cable Fill / Ties N/A
- 9. Aging of Plastic Ties N/A y 10. System Hardspots N/A j
- 11. Short Rods N/A i 1
j i Seismic Interaction Review Acceptance . 1. Proximate Features N/A . 2. Falling Hazards N/A 5 3. Differential Displacement N/A i
- 4. Isolated Outliers N/A 4
t 1 i i e i 1 l ? l J i 4
Nsw Ycrk PawIr Authsrity - FitzPItrick Nuclasr Pow:r Plant GIP Rev 2, 2/14/92 Cable and Conduit Raceway Review Sheet 2 of 3 Plant Area Summary Sheet g ID : RACE 008 (Rev. O) Plant Area : Cable Tunnels 286 ! L/ Building : CT Floor El. 286.00 l Room, Row / Col : COMMENTS l SRT: Arun Pal (NYPA), Steve Anagnostis (S&A)- week of 9/19/94 PLANT AREA: Cable tunnels on El 286 (adjacent to the relay room). TRAY TYPE: 4" deep PW Industries ladder tray; 24" and 30" wide l TRAY FILL: 0 % - 100 % TRAY SPANS: 6' to 8' CONDUlT SIZES: up to 5" CONDUlT SPANS: 6' - 8' TYPICAL SUPPORTS: 1
- 1. Floor to ceiling P1000 frames. One side of the frame consists of a vertical P1000 which is expansion anchored to the r/c floor at the bottom and beam clamped to building steel at the top.
The cross pieces (tiers) are bolted to the vertical P1000 on one end, and at the other end are attached to an embedded strut in the r/c wall with a P1075 fitting. These frames are 10' to 12" tall, support up to six (6) 24" trays, and are spaced at 6'- 8 '
- 2. 3/4" threaded rod trapeze hangers beam clamped to building steel. Hangers are up to 6' tall, support up to five 24" trays, and are spaced at 6' to 8'.
i 3. Floor / wall anchored P1000 frames. One side of the frame consists of a vertical P1000 which is expansion anchored to the r/c floor The cross pieces (tiers) are bolted to the vertical P1000 on one end, and at the other end are anchored to an r/c wall. The frames are about 3' tall, support up to 10 conduit (3" diameter and up), and are spaced at 4'.
- 4. Floor-to-ceiling frames similar to those in the cable spreading room.. They are 10'- 12' high, support up to seven (7) 30" trays, and are spaced at 6' to 8'.
- 5. Conduit rigidly anchored to the r/c floor.
LAR: None, covered by LARs from other areas. Evaluated by: Y, Date: 7/) , /9N r4 " f
Attachment:
Pictures
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i j New York Power Authority - FitzPatrick Nuclear Power Plant GIP Rev 2, 2/14/92 Cable and Conduit Raceway Review Sheet 3 of 3 l l Plant Area Summary Sheet ! ID : RACE 008 (Rev. O) Plant Area : Cable Tunnels 286 l Building : CT Floor El. 286.00 l Room, Row / Col PICTURES
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l N:;w York P;w:r Authority - FitzP2 trick Nuclair Powir Pl:nt GlP Rsv 2, 2/14/92 Cable and Conduit Raceway Review Shest 1 of 2 g Plant Area Summary Sheet ID : RACEOO9 (Rev 0) Plant Area : Electrical Bay _ (,N Building : EB Floor El. : 272.00 l Room, Row / Col : Check List inclusion Rule Review Acceptance
- 1. Cable Tray Span N/A
- 2. Conduit Span Yes
- 3. Tie Downs N/A
- 4. Channel Nuts Yes
- 5. Rigid Boots N/A
- 6. Beam Clamps Yes
- 7. Cast Iron Inserts N/A ___
Other Seismic Performance Concern Review Acceprce
- 1. Anchorage Yes
- 2. Welded Connections Yes _
- 3. Concrete Condition Yes
- 4. Corrosion N/A
- 5. Sagging Raceways N/A
- 6. Broken or Missing Components and Sharp Edges N/A
- 7. Restraint of Cables N/A
- 8. Cable Fill / Ties N/A >
(' 9. Aging of Plastic Ties N/A ( 10. System Hardspots N/A
- 11. Short Rods N/A Seismic Interaction Review Acceptance
- 1. Proximate Features N/A
- 2. Falling Hazards N/A l
- 3. Differential Displacement N/A
- 4. Isolated Outliers N/A
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N2w Ycrk Pawcr Auth:rity - FitzPatrick Nucl: r Powtr Plant GIP Rsv 2, 2/14/92 Cable and Conduit Raceway Review Sheet 2 of 2 Plant Area Summary Sheet j' ID : RACE 009 (Rev. 0) Plant Area : Electrical Bay d Building : EB Floor El. 272.00 l Room, Row / Col : COMMENTS l l SRT: Arun Pal (NYPA), Steve Anagnostis (S&A)- week of 9/19/94 i PLANT AREA: East and West Electrical Bays, El 272. i 1 TRAY TYPE: none TRAY FILL: n/a TRAY SPANS: n/a
)
CONDUlT SIZES: 1" to 4" CONDUlT SPANS: < GlP albwables Note that most cable to the elec'rical equipment in this area comes up through fbor penetrations from the cable tunnels below. TYPICAL SUPPORTS:
- 1. Conduit rigidly anchored (or on small, stiff hangers) to r/c walls, r/c ceilings, and block walls. All the block walls in this area were evaluated in the 80-11 program.
LAR: None. Evaluated by: Date: 7/2 /9P O / r A 1 9/4/SC I g. O
N:;w Ycrk Pow:r Authority - FitzPatrick Nucistr Powsr Pirnt GIP Rev 2, 2/14/92 Cable and Conduit Raceway Review Shset 1 of 4 Plant Area Summary Sheet g ID : RACE 010 (Rev. O) Plant Area : Emergency Diesel Generator Area
\ Building : EG Floor El. ; 272.00 l Room, Row / Col -
l Check List i inclusion Rule Review Acceptance
- 1. Cable Tray Span Yes
- 2. Conduit Span Yes l
- 3. Tie Downs Yes !
- 4. Channel Nuts Yes
- 5. Rigid Boots N/A
- 6. Beam Clamps Yes
- 7. Cast Iron Inserts N/A I I
Other Seismic Performance Concern Review Acceptance
- 1. Anchorage Yes
- 2. Welded Connections N/A
- 3. Concrete Condition Yes
- 4. Corrosion N/A
- 5. Sagging Raceways N/A
- 6. Broken or Missing Components and Sharp Edges N/A
- 7. Restraint of Cables N/A
- 8. Cable Fill / Ties N/A
- 9. Aging of Plastic Ties N/A O 10. System Hardspots
- 11. Short Rods Yes N/A Seismic Interaction Review Acceptance
- 1. Proximate Features N/A
- 2. Falling Hazards N/A
- 3. Differential Displacement N/A
- 4. Isolated Outliers N/A
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NIw Yerk Pcwcr Authsrity - FitzP trick Nuclarr Pownr Pirnt GIP Rsv 2, 2/14/92 Cable and Conduit Raceway Review Shsst 2 of 4 Plant Area Summary Sheet ID .: RACE 010 (Rev. 0) Plant Area : Emergency Diesel Generator Area Building : EG Floor El. : 272.00 l Room, Row / Col : COMMENTS SRT: Arun Pal (NYPA), Steve Anagnostis (S&A)- week of 9/19/94 PLANT AREA: Emergency Diesel Generator Areas, Elevation 272, including both the diesel generator rooms and the electrical equipment areas TRAY TYPE: 4" deep PW Industries ladder tray; 12" wide TRAY FILL: <= 50% TRAY SPANS: < 8' CONDUlT SIZES: 1" to 3' CONDUlT SPANS: < GlP allowables TYPICAL SUPPORTS:
- 1. In the electrical equipment areas - 3/4" rod trapeze hangers bolted to P1000s spanning between roof girders.
The height is about 15', spacing about 6', and they support three (3) 12" trays.
- 2. In the diesel generator rooms - 3/4" rod trapeze hangers beam clamped to roof girders. The height is about 15',
spacing about 6', and they support three (3) 12" trays.
- 3. Both areas - conduit rigidly anchored to building steel r/c walls, and 80-11 qualified block walls.
LAR: Type 1 support (see field sketch). Evaluated by: (( - Date: T/,2</*75 ,
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Attachment:
Pictures
Attachment:
Field Sketch i l l 4 O 0 l
5 ! New York Power Authority - FitzPatrick Nuclear Power Plant GIP Rev 2, 2/14/92 Cable and Conduit Raceway Review Sheet 3 of 4 f Plant Area Summary Sheet l O ID : RACE 010 (Rev. 0) Building EG Plant Area : Emergency Diesel Generator Area Floor El. : 272.00 l Room, Row / Col , l P_LCIUfES i l l t . ,' -
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N2w York Powsr Auth:rity - FitzP: trick Nucisar Pow r Pl:nt GIP Rsv 2, 2/14/92 , Cable and Conduit Raceway Review Shsst 4 of 4 l Plant Area Summary Sheet [ ID : RACE 010 (Rev. O) Plant Area : Emergency Diesel Generator Area
\, Building : EG Floor El. : 272.00 l Room, Row / Col :
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N2w Ycrk Psw:r Auth:rity - FitzPatrick Nucistr Pow:r Pl:nt GIP Rsv 2, 2/14/92 Cable and Conduit Raceway Review Shzet 1 of 3 Plant Area Summary Sheet ID : RACE 011 (Rev. 0) Plant Area : Service Water Pump Area V Building : SP Floor El. : 256.00 l Room, Row / Col . Check List inclusion Rule Review Acceptance
- 1. Cable Tray Span Yes
- 2. Conduit Span Yes
- 3. Tie Downs N/A
- 4. Channel Nuts Yes
- 5. Rigid Boots N/A
- 6. Beam Clamps N/A
- 7. Cast iron Inserts N/A Other Seismic Performance Concern Review Acceptance
- 1. Anchorage Yes
- 2. Welded Connections N/A
- 3. Concrete Condition Yes
- 4. Corrosion N/A
- 5. Sagging Raceways N/A
- 6. Broken or Missing Components and Sharp Edges N/A
- 7. Restraint of Cables N/A
- 8. Cable Fill / Ties N/A p
- 9. Aging of Plastic Ties N/A
- 10. System Hardspots N/A
- 11. Short Rods N/A Seismic Interaction Review Acceptance
- 1. Proximate Features N/A
- 2. Falling Hazards N/A
- 3. Differential Displacement N/A
- 4. Isolated Outliers N/A
~ +
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NIw Ycrk P:w;r Auth:rity - FitzP; trick Nucl2Ir Pswtr Plint GlP Rsv 2, 2/14/92 Cable and Conduit Raceway Review Shsst 2 of 3 i Plant Area Summary Sheet O ID : RACE 0111Rev. 0) Plant Area : Service Water Pump Area Building : SP Floor El. : 256.00 l Room, Row / Col : COMMENTS SRT: Arun Pal (NYPA), Steve Anagnostis (S&A)-week of 9/19/94
' PLANT AREA: Service Water Pumps Area (El 256). ,
TRAY TYPE: 4" deep PW Industries ladder tray; 12" wide TRAY FILL: < 25% TRAY SPANS: < 8' CONDUIT SIZES: 1" to 3* CONDUlT SPANS: < GIP allowables TYPICAL SUPPORTS: 1 3/4" rod trapeze hangers anchor with Phillips self-drill shell anchors. The height is about 4', spacing < 8', and they support three (3) 12' trays.
- 2. Same as (1) but on one side the cross pieces are anchored to an r/c wall with P1075 fittings.
- 3. Conduit rigidly anchored to r/c walls and ceilings, and 80-11 qualified block walls.
- 4. Lightly loaded 1/2" threaded rod trapeze hangers lightly loaded with a few conduit.
r I LAR: None, enveloped by LARs from other areas. ( j Evaluated by: [ // Date: F/)r/97 bl1)
Attachment:
Pictures
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New York Power Authority - FitzPatrick Nuclear Power Plant GIP Rev 2, 2/14/92 Cable and Conduit Raceway Review Sheet 3 of 3 Plant Area Summary Sheet O ID : RACE 011 (Rev. 0) Building SP Plant Area : Service Water Pump Area Floor El. 256.00 l Room, Row / Col - PICTURES a l
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Type 1 support Type 2 support O J Type 4 support Type 5 support i i l l 4 l
. - - _ . - -. __ ._- __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ -_ -_________.1
M N;w Ycrk Psw:r Auth:rity - FitzP trick Nucl;sr Pawcr Pirnt GIP Rsv 2, 2/14/92 Cable and Conduit Raceway Review Sheet 1 of 3 Plant Area Summary Sheet t i ID : RACE 012 (Rev. 0) Plant Area : Battery Rooms V Building : BR Floor El. 272.00 l Room, Row / Col : Check. Uni inclusion Rule Review Acceptance
- 1. Cable Tray Span Yes
- 2. Conduit Span Yes
- 3. Tie Downs N/A
- 4. Channel Nuts Yes
- 5. Rigid Boots N/A
- 6. Beam Clamps Yes
- 7. Cast iron Inserts N/A Other Seismic Performance Concem Review Acceptance
- 1. Anchorage Yes
- 2. Welded Conriections N/A
- 3. Concrete Condition Yes
- 4. Corrosion N/A
- 5. Sagging Raceways N/A S. Broken or Missing Components and Sharp Edges N/A
- 7. Restraint of Cables N/A
- 8. Cable Fill / Ties N/A
- 9. Aging of Plastic Ties N/A
,j 10. System Hardspots N/A
- 11. Short Rods N/A Seismic Interaction Review Acceptance
- 1. Proximate Faatures N/A
- 2. Falling Hazards N/A
- 3. Differential Displacement N/A
- 4. Isolated Outliers N/A
~ +
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1 N2w Ycrk P:w:r Auth::rity - FitzPatrick Nucl:2r Pow:r Pirnt GlP Rav 2, 2/14/92 I Cable and Conduit Raceway Review Shsst 2 of 3 l Plant Area Summary Sheet ID : RACE 012 (Rev. O) Plant Area : Battery Rooms b Building : BR Floor El. : 272.00 l Room, Row / Col : COMMENTS 1 SRT: Arun Pal (NYPA), Steve Anagnostis (S&A)-week of 9/19/94 PLANT AREA: Battery Rooms (El 272). This includes the battery cubicles, adjacent electrical equipment and HVAC areas, and the hallway outside the battery cubicles. TRAY TYPE: 4" deep PW Industries ladder tray; 24" and 30" wide TRAY FILL: up to 100% TRAY SPANS: 6' CONDUlT SIZES: 1" to 3" CONDUlT SPANS: < GIP allowables TYPICAL SUPPORTS: 1 3/4" rod trapeze hangers beam clamped to building steel. The height is 1' to 4', spacing 6', and they support up to three trays.
- 2. Same as (1) but on one side the cross pieces are anchored to an r/c wall with P1075 fittings.
- 3. Conduit rigidly anchored to r/c walls and ceilings.
g LAR: None, enveloped by LARs from other areas. t Evaluated by:
,/ C e V Date: 7/J//W
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Attachment:
Pictures > LJ 4
New York Power Authority - FitzPatrick Nuclear Power Plant GIP Rev 2, 2/14/92 Cable and Conduit Raceway Review Sheet 3 of 3 Plant Area Summary Sheet O ID : RACE 012 (Rev. 0) Building : BR Plant Area : Battery Rooms Floor El. : 272.00 l Room, Row / Col : PICTURES af ( 'sf ' W' -{ {i _, .. .s i i.: , -
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Nsw York Pawar Authority - FitzP . trick Nuclear Power Pl nt GIP Rev 2, 2/14/92 Cable and Conduit Raceway Review Shsst 1 of 5 s Plant Area Summary Sheet ID : RACE 013 (Rev. O) Plant Area : Cable Spreading Room \~ Building : CS Floor El. : 272.00 l Room, Row / Col : Check List inclusion Rule Review Acceptance
- 1. Cable Tray Span Yes
- 2. Conduit Span N/A
- 3. Tie Downs N/A
- 4. Channel Nuts Yes
- 5. Rigid Boots N/A
- 6. Beam Clamps Yes
- 7. Cast Iron Inserts N/A Other Seismic Performance Concern Review Acceptance
- 1. Anchorage Yes
- 2. Welded Connections N/A
- 3. Concrete Condition Yes
- 4. Corrosion N/A
_5. Sagging Raceways N/A
- 6. Broken or Missing Components and Sharp Edges N/A
- 7. Restraint of Cables N/A
- 8. Cable Fill / Ties N/A
- 9. Aging of Plastic Ties N/A
- 10. System Hardspots N/A
- 11. Short Rods N/A Seismic Interaction Review Acceptance
- 1. Proximate Features N/A
- 2. Falling Hazards N/A
- 3. Differential Displacement N/A
- 4. Isolated Outliers N/A
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New York Power Authority - FitzPatrick Nuclear Power Plant GIP Rev 2, 2/14/92 Cable and Conduit Raceway Review Sheet 2 of 5 Plant Area Summary Sheet ID : RACE 013 (Rev. O) Plant Area : Cable Spreading Room l Building : CS Floor El. 272.00 l Room, Row / Col ' COMMENTS SRT: Arun Pal (NYPA), Steve Anagnostis (S&A)- week of 9/19/94 PLANT AREA: Cable spreading room, El 272. TRAY TYPE: 4" deep PW Industries ladder tray; 24" and 30" wide TRAY FILL: <50% TRAY SPANS: 6'to 7' CONDUlT SIZES: 1" to 3' CONDUlT SPANS: < GIP allowables TYPICAL SUPPORTS:
- 1. Floor to ceiling P1000 frames. The frames are beam clamped to building steel at the top, :nd expansion anchored to the r/c floor at the bottom. The height is about 10", spacing is 6', and they support up to 7 trays.
- 2. Conduit rigidly anchored to r/c walls and ceilings. j LAR: Type 1 support (see field sketch).
Evaluated by: /( l y bN Date: 7 Jr /97
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Attachment:
Pictures
Attachment:
Field Sketch i i
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New York Power Authority - FitzPatrick Nuclear Power Plant GIP Rev 2, 2/14/92 Cable and Conduit Raceway Review Sheet 3 of 5 Plant Area Summary Sheet O ID : RACE 013 (Rev. 0) Building : CS Plant Area : Cable Spreading Room Floor El. 272.00 l Room, Row / Col - PICTURES l 1 __ I g. A:. 6 - ~ r DC7- 'F 9: 1
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N:;w Yerk Pawar Auth:rity - FitzPatrick Nucirr Pawir Pl;nt GIP Rsv 2, 2/14/92 Cable and Conduit Raceway Review Sh::st 4 of 5 Plant Area Summary Sheet [\ ID : RACE 013 (Rev. O) Plant Area : Cable Spreading Room Building : CS Floor El. 272.00 l Room, Row / Col : Field Sketch 7; , ---- 2 '" _f M.
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- w Ycrk Pow:r Auth rity - FitzPatrick Nucistr Powzr Pirnt GIP Rav 2, 2/14/92
- Cable and Conduit Raceway Review Shset 1 of 5 l l Plant Area Summary Sheet i- ID
- RACE 014 (Rev. 0) Plant Area : Relay Room l Building : RR Floor El. : 286.00 l Room, Row / Col Check List I Inclusion Rule Review Acceptance
- 1. Cable Tray Span Yes
- 2. Conduit Span Yes
- 3. Tie Downs N/A
- 4. Channel Nuts Yes
- 5. Rigid Boots N/A i
- 6. Beam Clamps Yes
- 7. Cast Iron inserts N/A Other Seismic Performance Concern Review Acceptance
- 1. Anchorage Yes
- 2. Welded Connections N/A
- 3. Concrete Condition Yes
- 4. Corrosion N/A
- 5. Sagging Raceways N/A
- 6. Broken or Missing Components and Sharp Edges N/A
- 7. Restraint of Cables Yes
- 8. Cable Fill / Ties N/A
- 9. Aging of Plastic Ties Yes O 10. System Hardspots
- 11. Short Rods N/A Yes t
Seismic Interaction Review Acceptance
- 1. Proximate Features N/A
- 2. Falling Hazards N/A
- 3. Differential Displacement N/A
- 4. Isolated Outliers N/A
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NIw Ycrk P:w:r Auth::rity - FitzP; trick Nucisar Psw;r Pirnt GlP Rav 2, 2/14/92 Cable and Conduit Raceway Review Shut 2 of 5 { Plant Area Summary Sheet . '[~
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ID : RACE 014 (Rev. O) Building : RR Plant Area : Relay Room Floor El. 286.00 l Room, Row / Col : l l COMMENTS ! SRT: Arun Pal (NYPA), Steve Anagnostis (S&A)- week of 9/19/94 , PLANT AREA: Relay room El 286. l TRAY TYPE: 4" deep PW Industries ladder tray; 30" wide l TRAY FILL: <= 50% TRAY SPANS: about 6' CONDUlT SIZES: up to 4" CONDUlT SPANS: < GlP allowables TYPICAL SUPPORTS:
- 1. Ceiling / wall mounted hanger. A 3/4" threaded rod expansion anchored to the ceiling; the P 1000 cross pieces are attached to the rod on one end and anchored to an r/c wall on the other end. The hangers have a total height of about 12', are spaced at 6', and support up to 9 trays.
- 2. 3/4" threaded rod trapeze hangers anchored with either a shell anchor or a beam clamp. The hangers have a total height of about 6', are spaced at about 6', and support up to 5 trays.
3.1/2" threaded rod trapeze hangers anchored with beam clamps. About 6' tall, spaced at 6', and support up to 6 conduit on one tier.
- 4. Conduit rigidly anchored to r/c walls.
LARs (see field sketch):
- 1. Type 1 support
- 2. "Long" Type 2 support
- 3. "Short" Type 2 support Evaluated by:
Date: T /93
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Attachment:
Pictures ~ t Attachmer.;: Field Sketch nv
I New York Power Authority - FitzPatrick Nuclear Power Plant GIP Rev 2, 2/14/92 Cable and Conduit Raceway Review Sheet 3 of 5 l i Plant Area Summary Sheet ID : RACE 014 (Rev. 0) Plant Area : Relay Room j Building : RR Floor El. ; 286.00 l Room, Row / Col : ( 4 ! PICTURES a
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N;w Ycrk P:wIr Auth:rity - FitzPztrick Nucl:nr Pawrr Pl;nt GIP Rsv 2, 2/14/92 Cable and Conduit Raceway Review Shest 4 of 5 Plant Area Summary Sheet [ ID : RACE 014 (Rev. O) Plant Area : Relay Room V Building : RR Floor El. 286.00 l Room, Row / Col : Field Sketch e t f J2
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N::w Ycrk Pswnr Auth:rity - FitzPctrick Nuclasr Powcr Pirnt GIP Rsv 2, 2/14/92 Cable and Conduit Raceway Review Shset 5 of 5 , Plant Area Summary Sheet ID : RACE 014 (Rev. 0) Plant Area : Relay Room \ Building : RR Floor El. : 286.00 l Room, Row / Col : i t o l l l 1 i i
N:w Ycrk P wxr Auth:rity - FitzPatrick Nucirir Paw:r Pl nt GIP Rsv 2, 2/14/92 Cable and Conduit Raceway Review Shsst 1 of 2 Plant Area Summary Sheet ID : RACE 015 (Rev. 0) Plant Area : Control Room A Building : CR Floor El. : 300.00 l Room, Row / Col : Check List inclusion Rule Revbw Acceptance
- 1. Cable Tray Saan N/A
- 2. Conduit Spaa Yes
- 3. Tie Downs N/A
- 4. Channel Nuts Yes
- 5. Rigid Boots N/A
- 6. Beam Clamps N/A
- 7. Cast Iron Inserts N/A Other Seismic Performance Concern Review Acceptance
- 1. Anchorage Yes
- 2. Welded Connections N/A
- 3. Concrete Condition Yes
- 4. Corrosion N/A
- 5. Sagging Raceways N/A
- 6. Broken or Missing Components and Sharp Edges N/A
- 7. Restraint of Cables N/A
- 8. Cable Fill / Ties N/A e 9. Aging of Plastic Ties N/A ,
! 10. System Hardspots N/A
- 11. Short Rods N/A Seismic Interaction Review Acceptance
- 1. Proximate Features N/A
- 2. Falling Hazards N/A
- 3. Differential Displacement N/A
- 4. Isolated Outliers N/A v
_.- . - . -. - .. . - - __ -. _ . .. . . . - = -. N;w Ycrk Psw;r Auth:rity - FitzP; trick Nucl::r Pow:r Pirnt GIP Rav 2, 2/14/92 Cable and Conduit Raceway Review Sheet 2 of 2
- Plant Area Summary Sheet ID : RACE 015 (Rev. 0) Plant Area : Control Room Building : CR Floor El. : 300.00 l Room, Row / Col : i
. COMMENTS SRT: Arun Pal (NYPA), Steve Anagnostis (S&A)-week of 9/19/94 PLANT AREA: Control Room, El 300.
P TRAY WPE: none TRAY FILL: n/a TRAY SPANS: n/a CONDUlT SIZES: up to 4" CONDUlT SPANS: < GlP allowables WPICAL SUPPORTS:
- 1. A few conduit above the false ceiling rigidly anchored to building steel.
LAR: None. Evaluated by: Date: /,/,2 /,/h 7 , 9[ LIT o u l
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N:w Ycrk Pcwrr Autharity - FitzP; trick Nucl:Cr Pswer Picnt GlP Rav 2, 2/14/92 Cable and Conduit Raceway Review Shsst 1 of 3 Plant Area Summary Sheet , ID : RACE 016 (Rev. 0) Plant Area : Control Room A/C Area b Building : AD Floor El. 300.00 l Room, Row / Col : Check List inclusion Rule Review Acceptance
- 1. Cable Tray Span Yes
- 2. Conduit Span Yes
- 3. Tie Downs N/A
- 4. Channel Nuts Yes
- 5. Rigid Boots N/A
- 6. Beam Clamps Yes
- 7. Cast iron Inserts N/A Other Seismic Performance Concem Review Acceptance
- 1. Anchorage Yes
- 2. Welded Connections Yes
- 3. Concrete Condition Yes
- 4. Corrosion N/A
- 5. Sagging Raceways N/A
- 6. Broken or Missing Components and Sharp Edges N/A
- 7. Restraint of Cables N/A
- 8. Cable Fill / Ties N/A Q /
- 9. Aging of Plastic Ties
- 10. System Hardspots N/A N/A
- 11. Short Rods N/A Seismic Interaction Review Acceptance
- 1. Proximate Features N/A I
- 2. Falling Hazards N/A
- 3. Differential Displacement N/A
- 4. Isolated Outliers N/A
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N;w Ycrk P:wcr Auth:rity - FitzPctrick Nucirr P wcr PIInt GIP R3v 2, 2/14/92 I Cable and Conduit Raceway Review Shut 2 of 3 Plant Area Summary Sheet ID : RACE 016 (Rev. 0) Plant Area : Control Room A/C Area V Building : AD Floor El. : 300.00 l Room, Row / Col . COMMENTS SRT: Arun Pal (NYPA), Steve Anagnostis (S&A)- week of 9/19/94 PLANT AREA: Control Room HVAC area, El 300. TRAY TYPE: 4" deep PW Industries ladder tray; 24" wide TRAY FILL: <= 50% TRAY SPANS: 8' CONDUlT SIZES: < 2" CONDUlT SPANS: < GlP allowables ; TYPICAL SUPPORTS:
- 1. Two trays on c welded steel bracket rigidly anchored to an r/c wall.
' 2. Conduit rigidly an:hored to r/c walls and platform steel.
LAR: None. Evaluated by: J/ Date: F/,2r/D F f ( ? O
- 9/usr-G V^
Attachmont: Pictures i 8 I I
New York Power Authority - FitzPatrick Nuclear Power Plant GIP Rev 2, 2/14/92 Cable and Conduit Raceway Review sheet 3 of 3 l Plant Area Summary Sheet ID : RACE 016 (Rev. 0) Plant Area : Control Room A/C Area Building : AD Floor El. 300.00 l Room, Row / Col - j PICTURES
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N;w Ycrk Psw;r Authority - FitzPAtrick Nucisir Pcwsr PIInt GIP R3v 2, 2/14/92 Cable and Conduit Raceway Review Shsst 1 of 2 Plant Area Summary Sheet !
) ID : RACE 017 (Rev. 0) Plant Area : CAD Building !
(LM Building : CB Floor El. t 272.00 l Room, Row / Col : Check List l Inclusion Rule Review Acceptance
- 1. Cable Tray Span N/A
- 2. Conduit Span Yes
- 3. Tie Downs N/A
- 4. Channel Nuts Yes
- 5. Rigid Boots N/A
- 6. Beam Clamps N/A
- 7. Cast Iron Inserts N/A Other Seismic Performance Concem Review Acceptance
- 1. Anchorage Yes
- 2. Welded Connections N/A
- 3. Concrete Condition Yes
- 4. Corrosion N/A
- 5. Sagging Raceways N/A
- 6. Scoken or Missing Components and Sharp Edge? N/A
- 7. Restraint of Cables N/A
- 8. Cable Fill / Ties N/A A 9. Aging of Plastic Ties N/A
- 10. System Hardspots N/A
- 11. Short Rods N/A Seismic Interaction Review Acceptance
- 1. Proximate Features N/A
- 2. Falling Hazards N/A
- 3. Differential Displacement N/A
- 4. Isolated Outliers N/A
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_. ~. __ . .. . N:w Ycrk Paw:r Auth:rity - FitzPstrick Nucinr Psw:r PI nt GlP Rsv 2, 2/14/92 Cable and Conduit Raceway Review Shsst 2 of 2
, Plant Area Summary Sheet ID : RACE 017 (Rev. 0) Plant Area : CAD Building (N
Building : CB Floor El. : 272.00 l Room, Row / Col : GQMMENTS SRT: Arun Pal (NYPA), Steve Anagnostis (S&A)-week of 9/19/94 PLANT AREA: CAD shack, El 272. TRAY TYPE: none TRAY FILL: n/a TRAY SPANS: n/a CONDUlT SIZES: up to 3" CONDUlT SPANS: < GlP allowables TYPICAL SUPPORTS:
- 1. A few conduit rigidly anchored to the ceiling.
LAR: None Evaluated by: Date: T /2,1/ 9; ct Yh h/h9-O U
N:;w Yerk Pswrr Auth:rity - FitzPItrick Nuclar Pcwcr PI:nt GIP Rev 2, 2/14/92 Cable and Conduit Raceway Review Shsst 1 of 2
- Plant Area Summary Sheet
[ ID : RACE 018 (Rev. 0) Plant Area : Drywell and Steam Tunnel Building : PC Floor El. ; 272.00 l Room, Row / Col : Check List inclusion Rule Review Acceptance
- 1. Cable Tray Span N/A
- 2. Conduit Span Yes
- 3. Tie Downs N/A
- 4. Channel Nuts Yes
- 5. Rigid Boots N/A
- 6. Beam Clamps N/A
- 7. Cast Iron Inserts N/A Acceptance '
_Other Seismic Performance Concern Review
- i. Anchorage Yes
- 2. Welded Connections Yes
- 3. Concrete Condition Yes
- 4. Corrosion N/A
- 5. Sagging Raceways N/A
- 6. Broken or Missing Components and Sharp Edges N/A
- 7. Restraint of Cables N/A
- 8. Cable Fill / Ties N/A
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- 9. Aging of Plastic Ties
- 10. System Hardspots N/A N/A
- 11. Short Rods N/A Seismic Interaction Review Acceptance
- 1. Proximate Features Yes
- 2. Falling Hazards Yes
- 3. Differential Displacement Yes
- 4. Isolated Outliers Yes
N;w Ycrk Paw;r Auth:rity - FitzP; trick Nucl2:r P w;r Pl:nt GIP Rsv 2, 2/14/92 Cable and Conduit Raceway Review Shsst 2 of 2 Plant Area Summary Sheet Plant Area : Drywell and Steam Tunnel t V) ID : RACE 018 (Rev. 0) Building : PC Floor El. : 272.00 l Room, Row / Col : COMMENTS SRT: Walter Djordjevic (S&A) and Steve Anagnostis (S&A)- 1/5/95 PLANT AREA: Drywell and main steam tunnel. TRAY TYPE: none TRAY FILL: n/a TRAY SPANS: n/a i CONDUlT SIZES: up to 4" ' CONDUlT SPANS: <10',6' to 8' typical. TYPICAL SUPPORTS:
- 1. Conduit rifidly anchored to r/c walls, floor, ceiling.
LAR: None Evaluated by: Date: )T/9 F
/ j 1- '
0 0 - r/a er , t U . l l I
p Appendix D - Limited Analytical Reviews (LARs) O 1. INTRODUCTION This Limited Analytical Review (LAR), performed within the scope of Unresolved Safety issue (USI) A46, evaluates the structural integrity of cable tray and conduit supports which have been chosen as representative, worst case examples of the major different types of raceway support configurations within JAFNPP. Ten sample supports have been chosen from the plant raceway support systems for evaluation. Section 2 summarizes the results. Section 3 lists the allowables used in the evaluations. Section 4 summarizes other inputs to the evaluations. Section 5 contains the references. Section 6 contains the calculations. i f rs !
/ +
I I I i I f O JAFNPP A-46 Seismic Evaluation Report September 1995 Appendix D, page 1/6 j
- 2.
SUMMARY
OF RESULTS / jnteraction Values h The critical interaction values for each of the raceway support evaluations in this LAR are summarized in Table 1 below. Table 1 CriticalInteraction Values LAR # Support Description Interaction Load Case LAR001 Location: Reactor Building Crescents 0.43 Dead Load Wall bracket, three tiers, Unistrut construction, anchored with expansion anchors. LAR002 Reactor Building Elevation 272 1.45 Dead Load [1] 3/4" threaded rod trapeze, seven tiers, bolted to 2.56 3x Dead Load Unistrut runner spanning between embedded Unistruts in the ceiling. LAR003 Cable Tunnels, Elevation 260 0.41 Dead Load 3/4" threaded rod trapeze,6 tiers, anchored with 0.64 3x Dead Load 3/4* shell anchors. LAR004 Cable Tunnels, Elevation 260 0.41 Dead Load [2] 3/4" threaded rod trapeze,6 tiers, anchored by 1.13 3x Dead Load botting into embedded Unistruts. LAR005 Cable Tunnels, Elevation 260 0.41 Dead Load Wall bracket with 3/4' threaded rod vertical support at free end,6 tiers, bolted to embedded Unistrut LAR006 EDG Area, Elevation 272 0.40 Dead Load ( 5 3/4" threaded rod trapeze, 3 tiers, bolted to 0.70 3x Dead Load () Unistrut spanning between roof beams. LAR007 Cable Spreading Room, Elevation 272 0.55 Dead Load Floor-to-ceiling Unistrut frame,7 tiers, beam- 0.49 3x Dead Load clamped to building steel at the top, expansion 0.51 Latoral Load anchored to r/c slab at the bottom. LAR008 Relay Room, Elevation 286 0.41 Dead Load Wall bracket with 3/4" threaded rod vertical support at free end,9 tiers, expansion anchored to r/c wall. LAR009 Relay Room, Elevation 286 0.41 Dead Load 3/4" threaded rod trapeze,5 tiers, one rod 0.73 3x Dead Load expansion anchored to r/c ceiling, other rod beam clamped to building steel. LAR010 Relay Room, Elevation 286 0.50 Dead Load 3/4" threaded rod trapeze, 5 tiers, beam clamped 0.88 3x Dead Load to building steel. [1] Outlier, doesn't pass dead load. [2] Outlier, resolved using limit state evaluation (see calculation) l Yv JAFNPP A-46 Seismic Evaluation Report September 1995 Appendix D, page 2/6 l
- 3. ALLOWABLES p The following is a compilation of the allowables used in the LARs.
V : Structural Steel: All structural steel support members are assumed to be ASTM A36 with a minimum yield strength of 36 ksi. AISC Specification allowables for Allowable Stress Design (Ref. 5.1) are used for the dead load analysis. For other than dead load analyses, the allowable stress is increased to 0.9 Fy = 32.4 ksi. Weld Filler Metal: All welds are assumed to be E60xx. The allowable weld shear stress, based on Table J2.5 of Ref. 5.1, is 0.3 x 60 = 18 ksi for dead load analysis. For all other analyses,1.7 x 0.3 x 60 = 30.6 ksi is used. Unistrut Channels: Dimensions, properties, and allowables used to analyze Unistrut Channels are based on the manufacturer's catalog data provided in Reference 5.2. For dead load analysis, the allowable is the maximum bending moment: P1000: 5080 in-Ib Ref 5.2, page 23 P1001: 14,400 in-Ib Ref 5.2, page 23 For other than dead load analyses, these are increased by a factor of 1.7. Embedded Unistrut Channels: Per Reference 5.4, various JAFNPP concrete drawings (FC series), and field observations, the embedded channels used at JAFNPP are Unistrut P3270. Per Reference 5.2, p173, these have an allowable pullout load of 2000 lb per point load and 2000 lb/ft. This value is used for the dead load analysis and all other analyses. 3 Unistrut Hardware Comoonents: Dimensions, properties, and allowables used to analyze various Unistrut hardware components (brackets, fittings, nuts and bolts, etc.) are based on the manufacturer's catalog data provided in Reference 5.2. These values are used for the dead load analysis and all other analyses. , Concrete Exoansion Anchors: Per reference 5.4 and field observations, the expansion anchors used to anchor raceways supports at JAFNPP are Phillips Redhead Self-Drills or equivalents. Anchor bolt allowables are based on Tables C.2-1 and C.2-2 of the GlP (Reference 5.3) values for Phillips Redhead Self-Drills The required reduction factors are applied as follows: Anchor Type Per the above discussion, anchor bolts are either Phillips Self-Drill or equivalent. No capacity reduction based on anchor type is required. Tightness and Per GIP Section 8.3.8, tightness checks (or the Reduced inspection Attemative) Embedment Checks are required only for floor mounted anchors. Where floor-mounted anchors are used, the Reduced Inspection Altemative will be applied - a reduction factor of 0.75 multiplied by an additional reduction of 0.67 to meet the "one-third of anchors not available" requirement, for a total reduction factor of 0.50. I Concrete Strength The concrete compressive strength at JAFNPP is 3000 psi (see the JAFNPP FC Check drawing series). This requires a reduction factor of 0.75 in pullout and 0.95 in shear. Spacing, Edge Applied as required on a case-specific basis. Distance, and Concrete Crack Checks O JAFNPP A-46 Seismic Evaluation Report September 1995 Appendix D, page 3/6
Expansion anchor allowables based on the above are summarized below. O Colling/ Wall Mounted Floor Mounted V Size Tension Shear Tension Shear 3/8" 1.10 k 1.35 k 0.55 P 0.68 k 1/2" 1.72 k 2.26 k 0.86 k - 1.13 k 5/8" 2.38 k 3.60 k 1.19 k 1.80 k 3/4" 3.52 k 5.21 k 1.76 k 2.61 k I These values are used for the dead load analysis and all other analyses. l l l
- 4. INPUT DATA ' l l
Other data used in the LARs are summarized below. Cable Tray Weghts The weight per foot used in the LARs for the standard JAFNPP cable tray (24" wide I by 4" high) with 100% fill is 50 pounds per linear foot (Ref 5.3, page 8-38). This weight is linearly adjusted for trays of other widths and fill levels. y Condurt Weghts: The weights per foot for rigid steel conduit is as prot. sed by Reference 5.3 page 8-38. l Plant Area Summary Sheets: The raceway supports evaluated in the LARs were selected by the Seismic ! Review Team (SRT) that performed the raceway walkdown. The support geometries are documented in
.{
the Plant Area Summary Sheets (PASS), which are part of the project documentation. . I Lateral Load Evaluatens Three options are presented in the GlP, Ref. 3.6.3, Section 8.3.4 for ! cletermining the horizontal seismic acceleration to be used in lateral load evaluations. Acceleration values j O- for JAFNPP corresponding to each of the options are summarized below. j Elevation ZPA Option 1 Option 2 Option 3 TB 272 0.53 0.91 1.33 0.70 TB 300 0.22 0.91 0.55 0.70 i RB 272 0.20 0.91 0.50 0.70 ; RB 326 0.31 0.91 0.78 .n/a l RB 344 0.50 0.91 1.25 n/a ! RB 369 0.43 0.91 ']' 1.08 n/a { ZPA: 5% damped FRS, peak above 33 Hz, max of EW, NS l Option 1: 2g scaled by the maximum of SSE/ Bounding Spectrum (ZPA ratio of 0.15 / 0.33 controls) l Option 2: 2.5* Floor ZPA _ Option 3: 2.5*1.25*1.5*SSE ZPA (within 40' of grade) ! Option 1 is used in all cases. f, f E r I O JAFNPP A-46 Seismic Evaluation Report l; September 1995 Appendix D, page 4/6 3 i [ I
. . _ . . . . _ . _ . _ . , ._. = . _ . . _ . _ _ .. . ~ _ _ _ _ . . . _ _ _ _ . _ _ . . ._. . . _ . . .. . .
Rod Hanaer Fatious Evaluations: The rod fatigue bounding spectra provided in the GIP, Ref. 3.6.3, n Figure 8-9, are plotted below vs. the envelope of the JAFNPP 5% d amping floor response spectra for the s Reactor Building and the Turbine Building. These curves are used to determine the applicable bounding Jb-} curve in the Fatigue Evaluation Screening Charts, Figum 8-10 to 814 of the GlP. . 1 2.0 i i l ', emW o.75,', j
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%/ 5. REFERENCES 5.1 " Manual of Steel Construction, Allowable Stress Design",9th Edition, American institute of Stee! ,
Construction, Inc. Chicago, IL,1989. l 5.2 " General Engineering Catalog", No.12, North Americari Edition, Unistrut Corporation, Wayne, MI, ! 1992. ; t 5.3 " Generic Implementation Procedure (GIP), for Seismic Verification of Nuclear Plant Equipment", - , Revision 2, Corrected 2/14/92, Seismic Qualification Utility Group. i 5.4 "PASNY Nuclear Facility Specification for Galvanized Cable Tray James A. Fitzpatrick Nuclear Power Plant Purchase Order No. APO-63", Stone & Webster Engineering Corporation, J. O. No.11825, Revision 1, October 1,1970. I 5.5 "JAFNPP A-46 Floor Response Spectra Review", S&A Calculation 93C2803-C-001. O JAFNPP A-46 Seismic Evaluation Report September 1995 Appendix D, page 5/6 ! 1
- .a
- 6. CERTIFICATION (GIP EXHIBIT 8-2) 0 The following serves as certification for all of the Limited Analytiical Reviews (GIP Exhibit 8-2). Sketches are contained in the Plant Area Summary Sheets (Appendix D of this report). The calculations are attached; the calculation pages are numbered 1/46 through 46/46.
LAR # Support Description PASS # LAR001 Location: Reactor Building Crescents RACE 001 Wall brscket, three tiers, Unistrut construction, anchored with expansion anchors. LAR002 Reactor Building Elevation 272 RACE 003 3/4" threaded rod trapeze, seven tiers, bolted to Unistrut runner spanning between embedded Unistruts in the ceiling. ; LAR003 Cable Tunnels, Elevation 260 RACE 007 ; 3/4" threaded rod trapeze,6 tiers, anchored with 3/4" shell anchors. LAR004 Cable Tunnels, Elevation 260 RACE 007 3/4" threaded rod trapeze,6 tiers, anchored by bolting into embedded Unistruts. LAR005 Cabie Tunnels, Elevation 260 RACE 007 Wall bracket with 3/4" threaded rod vertical support at free end,6 tiers, bolted to embedded Unistrut j LAR006 EDG Area, Elevation 272 RACE 010 3/4" threaded rod trapeze,3 tiers, bolted to Unistrut spanning between roof i beams. , LAR007 Cable Spreading Room, Elevation 272 RACE 013 /O Floor-to-ceiling Unistrut frame,7 tiers, beam-clamped to building steel at the , (I LAR008 top, expansion anchored to r/c slab at the bottom. Relay Room, Elevation 286 l RACE 014 Wall bracket with 3/4" threaded rod vertical support at free end,9 tiers, expansion anchored to r/c wall. LAR009 Relay Room, Elevation 286 RACE 014 3/4" threaded rod trapeze, 5 tiers, one rod expansion anchored to r/c ceiling, other rod beam clamped to building steel. LAR010 Relay Room, Elevation 286 RACE 014 3/4" threaded rod trapeze, 5 tiers, beam clamped to building steel. CERTIFICATION: (Signatures of at least two Seismic Capability Engineers are required; one of whom is a licensed professional engineer.) Stechen Anaanostis 5 Print or Type Name 'Sigr(ature ' Date Frank B. Stille - 9 2 f Print or Type Name signature Date JAFNPP A-46 Seismic Evaluation Report September 1995 Appendix D, page 6/6
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