ML20199E267
| ML20199E267 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 11/17/1997 |
| From: | Sorensen J NORTHERN STATES POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| REF-GTECI-A-46, REF-GTECI-SC, TASK-A-46, TASK-OR GL-87-02, GL-87-2, TAC-M69474, TAC-M69475, NUDOCS 9711210149 | |
| Download: ML20199E267 (157) | |
Text
Northem States Power Company Prairie Island Nuclear Generating Plant leh M n e 6 9 November 17,1997 '
Generic Letter 87-02 U S Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Docket Nos. 50-282 License Nos. DPR-42 50-306 DPR-60 Response to Request for Additional Information on the Prairie Island Nuclear Generating Plant, Units 1 and 2, Resolution of Unresolved Safety issue A-46 (TAC Nos. M69474 and M69475)
By letter dated September 16,1997, NRC requested additional information regarding our November 20,1995 response to Generic Letter 87-02," Verification of Seismic Adequacy of Mechanical and Electrical Equipment in Operating Reactors, USI A-46."
Our response to that request is enclosed as Attachments 1 through 5 to this letter. This response contains no new NRC commitments, nor does it modify any prior commitments, though some actions are being completed early.
Please contact Jack Leveille (612-388-1121, Ext 4662) if you have any questions related to this letter.
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Joel P Sorensen 1/b i
Plant Manager c: Regional Administrator - Region Ill, NRC Senior Resident inspector, NRC NRR Project Manager, NRC Kris Sanda, State of MN J E Silberg lkkk}ikb i t
9711210149 971117 J
PDR ADOCK 0500o282 P
November 17,1997 Page 2 Attachments:
- 1. _ Response to NRC Request for Additional Information
- 2. - Equipment Outiler Resolutions
- 3. Relay Outiler Resolutions
- 4. ANCHOR Software Evaluations 5,' Calculations /S5WS c
4702 05. DOC s.-
1 UNITED STATES NUCLEAR REGULATORY COMMISSION NORTHERN STATES POWER COMPANY PRAIRIE ISLAND NUCLEAR GENERATING PLANT DOCKET NO. 50-282 50-306 Response to Request for Additional Information on the Prairie Island Nuclear Generating Plant, Units 1 and 2, Resolution of Unresolved Safety issue A-46 Northern States Power Company, a Minnesott..orpor.) tion, with this letter is rumitting information requested by NRC Request for Additional Information regarding Generic Letter 87-02.
This letter contains no restricted or other defense information.
NORTHERN STATES POWER COMPANY
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BY Jh
//Joel'P Sorensen Plant Manager Prairie Island Nuclear Generating Plant On this I day of kldVEm b N Q before me, a notary public in and for said County, personally appeared Joel P Sorensen, Plant Mar.ager, Prairie Island Nuclear Generating Plant, and being first duly swom acknowleoged that he is authorized to execute this document on behalf of Northern States Power Company, that he knows the contents thereof, and that to the best of his knowledge, information, and belief the statements made in it are true and that it is not interposed for delay.
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Page 1 of 19 Response to NRC Request for Additional Information - USl A-46 Prairie island Nuclear Generating Plant 1.
In tne letter of Reference 1, the licensee indicsies its intent to apply the USI A-46 methodology to future verification of seismic adequacy of any new or replacement equipment or parts, which may also imply to incluue equipment identified as part of Regulatory Guide (RG) 1.97 or TMI Action Plan item II.F.2.
However, the staff position in item 2 of Section 1.2.3 of the supplemental safety evaluation report (SSER) 2, which clarifies Section 2.3.3 of the generic implementation procedure (GIP)-2 regarding revision of plant licensing bases, is that any previous licensing commitments, such as for RG 1.97 and TMl Action Plan item II.F.2, are not superseded by the resolution methods of the GIP.
Clarify your commitment with regard to the applicability of the A-46 methodology to new and replacement Category 1 equipment included in the SSEL (safe-shutdown equipment list) that are associated with RG 1.97 or TMI Action Plan item II.F.2.
Response
We did not intend "...any new or replacement equipment..." to include superseding the conditions of SSER-2. We take no exception to Item 2 of Section 1.2.3 of the supplemental safety evaluation report (SSER)-2 clarifying Section 2.3.3 of GIP-2. In complying with RG 1.97 and TMl Action Plan item II.F.2, the seismic qualification requirements are identified in the USAR. For Category 1 equipment included in the SSEL that are essociated with RG 1.97 or TMl Action Plan item II.F.2, new and replacement equipment will continue to comply with the USAR.
2.
Referring to the in-structure response spectra (ISRS) provided in your 120-day-response to the NRC's request in Supplement No.1 to Generic Letter 87-02, the following information is requested:
- a. Identify structure (s) that have ISRS with 5% critical damping for elev-tions within 40-feet above the effective grade, which are higher in amplitude than 1,5 times the SQUG (Seismic Qualification Utilities Group) Bounding Spectrum.
Response
Prairie Island is a relatively deep soil site. As such, the response is strongly influenced by the soil stiffness. The floor response spectra for the auxiliary-reactor-turbine building comple; peak at about 3 Hz. Above about 3 R, 8702-05. doc
m:N none of the floor spectra exceed 1.5 times the SQUG Bounding Spectrum (1.5BS). As none of the Class of Twenty equipment was adjudged to have fundamental frequencies near or below 3 Hz, the answer to this question is that no structures have ISRS (5% damped) above 1.5BS for elevation within j
40' above effective grade above about 3 Hz.
- b. With respect to the comparison of equipment seismic capacity and seismic demand, indicate wh'ch method in Table 41 of GIP-2 was used to evaluate tho salsmic adequacy for equinment installed on the corresponding floors in the structure (s) identified in item (a) above. If you have elected to use method A in Table 4-1 of the GIP-2, provide a technicaljustification for not using the ISRS provided in your 120-day response.
Response
As noted above, since none of the equipment is adjudged to have a fundamental frequency as low as 3 Hz, no equipment falls into this category,
- c. It appears that some A-46 licenseec are making an incorrect comparison between their plant's safe shutdow1 earthquake (SSE) ground motion response spectnam and the SQUG Bounding Spectrum. The SSE ground motion responsa spectrum for most nuclear power plants is defined at the plar" N ndation level. The SQUG Bounding Spectrum is defined at the free field guund surface. For plants located at deep soll or rock sites, there may not be a significant difference tutween the ground motion amplitudes at the foundation level and those at the ground surface. However, for sites where a structure is founded on shallow soll, the amplification of the ground motion from the fcundation level to the ground surface may be significant. Clarify appropriateness of a direction comparison of the SQUG Bounding Spectrum with the Prairia Island plant ground motion spectrum.
Response
The Prairie Island site is not a shallow aoll site. The site is underlain by approximately 158'-185' of sandy alluvial soil over a 180' thick layer of competent sandstone of the Franconia Formation. The sandstone is underlain by other older sedimentary rocks. The Prairie Island maximum credible earthquake design spectrum anchored at 0.12g peak ground acceleration (PGA) is referred to throughout the Updated Safety Analysis Report (USAR) as ground acceleration dasign spectrum. As such, it is has been consistently interpreted as the free field ground surface spectrum.
Conservatively, this ground motion has been used as the input to the foundation level of the building mathematical models for both the structural stress and iesponse spectrum analyses. Similarly, the Regulatory Guide 1.60 motion (0.12g PGA) was also conservatively input at the foundation led kr the seismic analyses of the recently constructed DS/D6 Building.
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- d. For the structure (s) Ider't!fied in item (a) above, provide the ISRS designated according to the height above the effective grade. If the ISRS Identified in the 120-day response to Supplement No.1 to Generic Letter 87-02 was not used, provide the response spectra that were actually used to verify the seismic adequacy of equipment within the structures identified in item (a) above. Also, provide a comparison of these spectra to 1.5 times the Bounding Spectrum.
Response
As notad in a.) above, no ISRS exceed 1.5BS above approximately 3 Hz within 40' above effective grade.
3.
In the letter of Reference 2, the licensee submitted its updated commitment regarding the outiler resolution schedule. The proposed time frame to complete all outiler resolution actions ranges from the end of 1996 to the spring of 1999, depending on the determination whether a specific outlier will be resolved by analysis or by modification with or without plant outage, in addition, although 96 outiler equipment and 49 outlier relays were identified in the Summary Report and the Relay Evaluation Report of Reference 1, information regarding their resolution is not included in the reports. Elaborate on your plans for scheduling the resolution of identified outliers, and your evaluation in support of the conclusion that the licensing bases for the plant wil! not be affected by the outilers resolution schedule. A number of safety-related components in the safe shutdown path have been identified as outliers - thus rendering their seismic adequacy questionable and their conformance to the licensing bases uncertain.
Provide justification of your continued operation without immediately undertaking remedial action.
Response
GIP Part I, Section 2.2.5 describes in detail the guidelines used by Prairie Island in implementing its responsibility to reporting under the USl A-46 program.
GlP Part l, Section 2.2.5 states: " Failure of equipment to meet GoPinitial screening or outlier resolution guidelines does not, ofitself, give rise to a need for the licensee to consider a JCO or reporting under applicable reporting requirements unless the plant has modifiedits commitments to adopt the USI A-46 (GIP) methodology as its licensing basis for verifying the seismic adequacy of electrical and mechanical equipment, as set faith in Paragraph 2.3.3 below. If a determination is made that equipment failing to meet the gip initial screening or outlier resolution guidelines does not meet the existing plant licensing or design bases, inr!uding spe:ific plant mmmitments and requirements, the licensee must consider reportability and operability implications pursuant to Technical specifications and 870245aoc
Page 4 of 11 10CFR50.72, 50.73 and 50.9, among others as appropriate, including the need for JCO. Non-safety grade equipment selected for use in A-46 is not exempt from reporting requirements.
There is no independent requirement to notify the Staff when an outlier or equipment deficient against A-46 criteria, which is not a deliciency against the plant's licensing or design basis, will not be modified to conform to the A-46 guidelines. However, licensees will report unresolved A-46 outliers or equipment deficient against A-46 criteria to the NRC Staffin their final st mary reports. These reports willinclude an explanation of tha safety irt.plications of not modifying the outliers or equipment deficient against A-46 cn'teria. Tne Staff willJustify any requirement to modify these outliers under 10CFR50.109 as statedin Section 2.3.1 below."
The GIP methodology screens out equipment which passes a set of conseNative, generic, seismic adequacy criteria. Equipment which does not pass this screen is ident!!ied as an outlier and either is resolved to be consistent with the GlP or may be left as an unresolved outiler. The GIP-2 screening criteria are not part of the licensing basis at Prairie Island; therefore, not meeting the GIP-2 screening criteria does not, of itself, give rise tu nn operability or safety concern. The Selsmic Review Team (SRT) determined there was no reason to believe ' hat the equipment that was classified as an outlier, as a result of the GIP-2 screening process, did not meet the plant licensing or design basis.
Equipment outlier resolution schedules are shown on Attachment 2. Relay outiler resolution sahedules are shown on Attachment 3.
4.
Describe the extent to which the seismic margin methodology, described in the report EPRI NP-6041 ("A Methodology for Assessment of Nuclear Power Plant Seismic Margin"), was used in the Prairie Island A-46 program, including outller resolutions. Since this methodology is known to yield analytical results that are not as conservative as what might be obtained by following the GlP-2 guidelines, it is generally not acceptable for the A-46 program. Therefore, for each deviation from the GIP-2 guidelines, in situations where the margin methodology is utilized, identify the nature and the extent of the deviation, and provide the justification for its acceptance.
Response
The seismic margin methodology has not been used in any manner in the conduct of the Prairie Island A-46 assessment.
870245 doc
Anachment 1 Page 6 of 11 5.
Section 3.4 of the Summary Report states that one horizontal ISRS was used for both (North South and East-West) directions, Indicate whether the horizontal ISRS used for the USl A-46 program envelop both horizontal ISRS provided in the NSPC's 120-day response to Supplement No.1 to Generic Letter 87-02. If not, provide the technical bases that supports the validity of such an assumption and an explanation of how the results of the A-46 review with such an assumption are still adequate.
Response
The horizontal ISRS used for the A-46 program are the spectra submitted in NSPC's 120-day response to Supplement No.1 to Generic Letter 87-02 (120-day letter). As stated in Attachment 4' to NSPC's 120-day response,-
'The response acceleration spectra obtained at various points in the structure showed that the response is primarily due to deformation of the foundations ana that the responses due to earthquakes acting in the north-south and east-west directions were not significantly different. Therefore, the spectr.1 were combined for the two earthquake directions to facilitate their application in the seismic design and analysis of critical equipment and piping."
The spectra were converted from the 1/2% and 1% damped curves to 5%
dampea curves in order to make appropriato comparisons to the 5%
bounding spectrum.
6.
Section 3,4 of the Summary Report also states that two-thirds of the Housner ground response spectra with peak cround acceleration of 0.04g and 0.08g for OBE [ operating-basis earthquake) and SSE, respectively, were used as the vertical ISRS regardless of location. Indicate whether the vertical ISRS used for the USl A-46 program envelop the vertical ISRS provided in the NSPC's 120-day-response. If not, provide the technical bases that support the validity of such an assumption and an explanation of how the results of the A-46 review are still adequate.
Response
The vertical ISRS used for the A-46 program are the spectra submitted in NSPC's 120-day response to Supplement No.1 to Generic Letter 87-02 (120-day letter). The spectra were converted from the 1/2% and 1% damped curves to 5% damped curves for purposes of seismic analysis.
i i Page 3. J AB PS 04, Pioneer Senice & Ergineering Company, Prair/c IslandNuclear Generating Plant Earthquake Analysis: Reactor Auxiliary-Turbine Building Response Acceleration Spectra, Revised February 16, 1971.
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Discuss key examples of bo-called " rigorously analy::ed anchorages," as indicated on page 4-3 of the Summary Report, using hand calculations and the ANCHOR software package, and provide copies of the engineering calculations.
Also discuss a few example cases of anchorage verification based er results of tug tests conducted and provide a description of tne tests and appliwbie engineering justification for such an approach.
Response
Sample ANCHOR software evaluations for equipment MCC 2K1 (Motor Control Center 2K, Bus 1) and 145 201 (11 Tutbine Driven Auxillary Feedwater Pump) are included in Attachment 4. The ANCHOR calculations themselves are self-explanatory. As brief ANCHOR code background, the USNRC and its subcontractor Dr. James Unruh of Southwest Research Institute thoroughly reviewed the ANCHOR code and found it acceptable for use in the A-46 equipment anchorage evaluations. Briefly, ANCHOR performs a three-dimensional, SRSS like (actually combines loads by 100-40-40 rule) maximum capacity calculation and deterrrines a factor of safety with respect to the demand accelerations. All of the allowables and reduction factors are directly from Appendix C of the GIP.
Manual calculations are reserved for situations where the ANCHOR code is not suitable or for which existing calculations are adequate. Two sample SEWS evaluations for tank 053-381 and the Diesel Generator Panel (55300) are provided in Attachment 5.
Tank 053-381 is the control room chilled water expansion tank. It is anchored with concrete expansion anchors. A me:.ual calculation was performed to evalauate the anchorage. The Diesel Generator Eng/ Gen Panel (55300)is bolted and shimmed. Since the bolts are thus subject to some bending, the methodology from Case 1 of EPRI Report TR-103960 was used to assess anchorage adequacy. This calculetion is incorporated in the SEWS for the Diesel Generator Panel (55300).
The engineering justification used for a tug test on a small component is that the applied load is larger than any credible seismic demand, or, the small component is clearly ruggedly anchored and the tug test verifies no gross installation defects. One example case of a tug test anchorage verification is PNL 132, which is a small wall-mounted panel, it is 26 inches wide by 45 inches high by 6.5"in depth and is anchored to the wall with 8 - 3/8" concrete expansion anchors. The item was pull tested to greater than 75 pounds (conservative estimate) with no looseness detected and thus was judged acceptable for anchorage (documented in a SEWS provided in Attachment 5). As noted in the SEWS, the anchorage was not accessible as it was behind the panel. An example of a small, ruggedly anchored item is panel 8702 05 doc l
Attachmerd 1 Page 7 of 11 PNL 113. The item is a wall-mounted panel,20 inches wide,36 inches high, and 6 inches deep. It is anchored to a reinforced concrete wa!! with four 1/2" anchor bolts. The item was pu? tested to greater than 75 pounds and no aseness was detected. The anchorage was adjudged acceptable because the anchorage was clearly rugged since there were no gross installation defects and the capacity obviously far exceeds Cemand. The SCE judgments were documented in the SEWS provided in Attachment 5.
8.
With respect to Section 4.1.3 of the Summary Report, the second paragraph of page 4-7 reads: " Wall mounted equipment was excluded as allowed by the GIP
.... Identify the specific provision of GlP-2 that allows such an exemption from performing the needed tightness check.
Response
The tightness check is used to detect gross installations errors that would leave the anchor loose in the hole. Per Section 4.4.1 of the GIP anchors loaded in tension due to dead weight need not be tightness checked since the anchor set is effectively proof tested by the dead weight loading. Wall mounted panels often presented a case of inaccessible anchors, because wall anchors were hidden behind the panel, and only disassembly of the panel would gain access to the anchors. lu that case, the SCE relied on the dead load proof testing for upper anchors and tug testing at the bottom and sides to verify no gross installation defects. In all cases, wall mounted panels were small enough such that the tug test was a meaningful exercise in verifying no gross installation defects.
9.
The fourth item in Table 5-1 of the Summary Report consists of the licensee's interpretation on meeting the intent of caveats for a group of small solenoid valves mounted on small piping and tubing (<l"). It indicated that the Seismic Review Team accepted the seismic ruggedness of these valves by a tug test for meeting the intent of Bounding Spectrum Caveats 4 and 5 for Class 8. The staff notes that, as stated in GIP-2 page B.8-3, the earthquake experience data for equipment Class #8 are limited to valves mounted on piping at least 1" in diameter, and the only suggested option by GIP-2 for meeting the intent of the Caveats 4 and 5 is by analysis.' Provide an explanation on how the " tug test" can ensure seismic adequacy of the valves and their connected pipe or tubing.
Response
Per GlP Appendix B, the intent of the FOV/BS Caveat 4 is to assure that pipe stresses associated with eccentric valve loads are not excessive. In this case, although the line was less than 1", the valve was very much smaller than that allowed for a 1"line; thus, rendering the need to perform a stress analysis an unnecessary measure in the view of the SRT. The assessment 870MS doc
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of the 3/4"line deviation is performed by estimating the potential increase in stress relative to that considered acceptable under the GIP for a 1" line. As i
noted, in this case, the conclusion could be obtained through engineering Judgment in lieu of stress analysis.
With regard to the tug test, an example is SV-37460 for which the SEWS is provided in Attachment 5. The solenoid valve is mounted to a steel plate.
The free span of the attached tubing is only approximately 18"long (see photograph). A tug test with an estimated force of 20 pounds far exceeds i
any seismic inertial forces that would occur in a seismic event. SV 37022 is listed in Table 5-1 but was subsequently removed from the final SSEL.
However the SEWS of record still serves as an example for tug tests. SV-37022 is anchored to a concrete wall with screws using unknown inserts. See the SEWS for this item (Attachment 5) - specifically, the photograph. The ltem in question is quite small, with each estimated to weigh less than 1 pound. The 3/4" tubing between the wall-mounted solenoid valves is less than 12" long which provides no significant stresses to the solenoid valve body. The items were tug tested by the Seismic Capability Engineers (SCE) to an estimated 20 pounds and the anchorage was judged to be acceptable.
10.
The sixth item in the same Table 51 indicated that the piping loads applied to the cas'.-Iron body of a group of solenoid valves are low and that they meet the intent of Bounding Spectrum Caveat 2 for Class 8 equipment, based solely on the judgement of the Seismic Review Team. Provide more explanation to assure that, without analysis, the seismic stresses in the valve body due to piping loads are within established acceptable limit, such as less than 20% of the minimum l
ultimate tensi!e strength of the valve body material as suggested in GlP-2.
Response
The valves in question, SV-33133 & SV-33134, have a cast iron body. The valve is a 2.5" diameter valve with a solenoid actuator which is estimated to weigh less than 1 pound. As such, the actuator will not contribute in any significant manner to the valve body stress. The adjacent supports are approximately 4 feet c/c with the valve located at about mid span. The valve and pipe can be calculated to respond in the rigid range; thus, using the zero period acceleration for the Screenhouse at Elev. 695' (0.3g), the resulting seismic plus gravity stress is 1.35 ksi Assuming the worst grade of cast iron, the ultimate tensile capacity is about 20 ksi. Using 20% of the ultimate tensile capacity as an allowable stress still provides a generous margin for this valve. We consider that this foregoing numerical evaluation substantiates the veracity of the engineering judgment originally rendered.
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- E.NoY 11.
With respect to Table 5-1 of the Summary Report, deviations were made to meet the GlP requirements. Provide the anchorage analysis calculations for the racks and panels (ID 181, 2R1), charging pumps (ID 145-041), feedwater pumps (ID 145-201) and main control panels (ID B 1).
Response
Calculations are provided for rack / panels 181 and 2R1, charging pumps 145-041, feedwater pumps 145-201 and main control board B-1 in Attachment 5.
12.
Section 6.1 of the Summary Report in Reference i states that some deviations and technicaljustifications were developed for the review of the tanks and heat exchangers. Provide a sample evaluation for each of the vertical tanks (flat bottom as well as supported on skirts and structural legs, if any) and the horizontal tanks. The evaluation of the anchors that restrain the tank movement should also be provided. If NSPC used the seismic margin methodology described in the report EPRI NP-6041 for the tank evaluations, identify the nature and the extent of the deviation from GIP-2 guidelines, and provide the justification for its acceptance. Also, provide calculations for determining the seismic adequacy of the tanks (ID 053 251,135-021,153-021 and 253-021) using the methodology described in Section 7 of the GlP 2,
Response
Calculations are provided for 135-021 (RCP Seal Water Return Heat Exchanger), 153-021 (Volume Control Tank), and 253-021 (Volume Control Tank)in Attachment 5. Tank 053-251 is a buried tank for which no evaluation was performed but the SEWS is provided in Attachment 5.
There are no freestanding, flat bottom vertical tanks at Pra!rie Island on the SSEL. The RWST, a flat-bottom vertical tank, is not freestanding. It is a oncrete tank with a steel liner and is an integral compartment of the Auxiliary building. As previously noted, the seismic margin method was not used for the Prairie Island A-46 assessment.
As previously noted, Tank 053 251 is a buried tank for which no evaluation was performed. This tank was declared an outlier because the flexibility of the buried piping could not be determined from available documentation.
Heat Exchanger 135-021 is an example of a vertical heat exchanger. Tanks 153-021 and 253-021, the volume control tanks, are examples of tanks on legs.
Regarding NRC's request for additional sample evaluations of other tenk and heat exchanger design types, Tank 053-381, the control room chilled water expansion tank, is an example of a skirt supported vertical tank provided in. Tank 153-011, the pressurizer relief tank, is an example of a saddle supported horizontal tank provided in Attachment 5.
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Page 10 of 11 13.
Table 7-3 of the Summary Report provides a summary of the limited analytical reviews (LARs) for the selected cable and conduit raceways. Provide copies of 1
the calculations of the analyses for LAR Numbers 005 and 010.
Response
7 Calculations are provided for LAR Numbers 005 and 010 as requested in.
j 14.
Discuss the issue described in Information Notice 95-49 (" Seismic Adequacy of Thermo Lag Panels") regarding Thermo-Lag panels, in particular, the issue regarding seismic resistance capability of the cable tray and its support when appropriate weight and modulus of the Thermo-Lag are included in the analysis.
Response
Thermo-Lag panels were included in the LAR calculations when present.
They were considered as adding mass (weight), but not stiffness. The connection stiffnesses are not sufficient to consider significant added stiffness due to the Thermo Lag panels. As an update, Thermo-Lag is being removed.
15.
Table 8-1 of the Summary Report listed 96 outtlers found in 20 classes of equipment during licensee's USl A-46 walkdowns. However, no resolution of these outliers was provided in the report; neither were there methods proposed to resolve these outliers. Provide a brief description of implemented resolution, or as a minimum, provide a proposed method to be implemented for resolution, for each outller listed in Table 8-1.
Response
The niethods used to resolve outliers along with descriptions of implemented resolutions for equipment outliers are shown in Attachment 2.
16.
Table 8-1 of the Summary Report does not show any safe-shutdown items (i.e.,
equipment, tanks, heat exchangers. cable trays or conduit raceways) as outliers because they are located above Elevation (EL) 755 feet. However, the screen verification data sheets in Appendix C of the Summary Report do show several items located more than 40 feet above the effective grade (or above Elevation 755 feet), and these item were considered "OK"in meeting the seismic demand and caveats. Clarify whether any safety equipment is located above Elevation 755 feet and provide the bases for its acceptance.
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Page 11 of 11
Response
L Equipment located more than 40' above grade can be screened out by a favorable comparison of the appropriate floor response spectrum to 1.5 times j
the bounding spectrum (1.5BS). This was done for the equipment located on i
or above elevation 755' and is referred to as ABS (represents 1.5BS) vs.
CRS (conservative floor response spectrum) in the Screening Verification Data Sheets (SVDS). As an added point, tanks and raceways are not subject to elevation rdstrictions such as the 40' rule since they are not " capacity -
screened"in the manner that the GIP identified Class of Twenty equipment l
Is.
17.
Regarding the tightness check of expansion anchors performed on a representative number of mechanical 9nd electrical components, state whether the representative number meets the sample size for expansion anchor tightness check as listed on Table 0.2-4 of the GIP.
Response
The sampling procedure, as discussed in the GIP, was not used at Prairie Island. All accessible expansion anchors in floor-mounted equipment were checked for tightness. Only anchors that were not accessible due to physical encumbrances were not tightness checked. As the GIP allows, inaccessible anchors for which extraordinary measures or disassembly of the equipment would be required need not be tightness checked.
18.
The Relay Evaluation Report in Reference 1 Identified 49 outlier relays.
However, no resolution of these outilers was provided in the report; neither were there proposed methods to resolve these outliers. Provide a brief description of implemented resolution, or as a minimum, provide a proposed method to be implemented for resolution, of each outlier relay listed in Appendix l of the report.
Response
The methods used to resolve outtlers along with descriptions of implemented resolutions for relay outilers are shown in Attachment 3.
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Resolut6on of (quipment Outliers 11/1707
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Cet l ID 1
Outlier Finding l
Rosolut6pn Description Method l Resolution by A01 MCC 1 A81 The anchorage has lneuffic6ent Ro6pived by analysis of actual Analysis Completed capechy to resist the seismic demand, installation. Irrstructure seismic demand is less than anchorage t:spacity.
A01 MCC 1 AB2 The anchorap nas insuff6cient Resolved by analysis of actual Analysis Completed capacity to resist the seismic demand. snstallation. Irvstructure seismic demand is less than anchorage tapacity.
A01 MCC 2R1 The anchorage has insufficient Resolved by analysis of actual Analysis Completed capacity to resist the seismic demand. installation. Irvstructure seismic demand is less than anchorage capacity.
' 01 MCC 251 The anchoreDe hac insufficient Resolved by analysis of actual Analysis Completed A
capacity to resist the seismic demand. anstallation. in-structure seismic demand is less than anchorage capacity.
A02 MCC1K1 The RHR Block Lifting Fixtures stored Reloived by analysis of actuel Analysis Completed nearby present an interaction herard installation. Acceleration levels less than to the MCC.
required to slide and unhook lif ting fixture.
A03 MCCITAI The MCC's rest on 6 sets of 2 Resolved by analysis of actual Analysis Completed
' shims' (7/8' thick) causing bending in installation. Anchorage acceptable with the ent. hor bolts.
2.76* shims.
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A03 MCC ITA2 1he MCC's rest on 6 sets of 2 Resolved by analysis of actual Analysis Completed
' shims' (7/8' thick) causing bending in installation. Anchorage acceptable with the anchor bolts.
2.75* shims.
A04 MCC 1L2 These MCC's contain essential relays Podormed an analysis of actual Analysis &
Dec 97 and have potential seismic mstallation. For MCC IL2, additional Modificction interactions from nearby piping.
supports are necessary for the 1 1/2' line and the two 4* lines, installing new supports 1 1/2' and 4' lines.
A04 MCC 2K2 These MCC's contain essential relays Resolved by analysis of actual Analysis Completed and bsve potential seismic installation. For MCC 2K2, displacement interactions from nearby piping, is less than ger.
Page1
i i
Resoletion of Equipment Outlers 11/17/97 Cet i
ID l
OuWor Findne l
":.fr.J Pessetstion Method i Resolution bv A06 MCC 2LA2 The SRT obewrved that this MCC Resolved by analysisi J ectual Analysis &
Completed; Wolds _.
rocks about its wook sans when wutellet6on. Ar#; ape is acceptable.
Mod fication U2 Outage Dec 98 burrood, making the weiding at the However, additional woede for equivalent) base suspect, hetween MCC/ SHIM /EMDED as m c.;,.f:f will be 6mptomented 1
where possible.
l
{
A06 2 62/RTA An unbraced overhead room chiller Performed an analysis of actual Analysis &
Dec 97 supported on rod hangers may awing metallet6on for 21 ROD DRIVE ROOM Modification and break nearby water piping which FAN COLL UNIT,274 021. Additional would sprey the room. Also, a unit restrainte are ecossary. Restraints are heater hung on 10 ft long rode could being added, swing and brook its steem heating piping.
A06 2 62/RTD An unbraced overhood roorn chiller Performed an analysis of Sctual Analysis &
Dec 97 supported on rod hangers may swing 6netellation for 21 ROD DRIVE ROOM Modification and brook nearby water piping which FAN COIL UNIT,274-021, Additional would sprey the room. Also, e unit restreints are tweessary. Restraints are hester hung on 10 ft long rods could being added.
swing and tweak its steem heating piping.
A07.
2PZRHTRAIX A rod hung unit hoster could swing Unit heater is not required and is being Modification Dec 97 FMR and brook its piping spraying the eres.
removed.
AOS 046 271 Submersible pumps are not part of Resolved by review of seismic Documentation Completed GIP's earthquake emperience data qualification documentation which shows Review
- base, that seismic design criteria consistent with our licensing besle was part of the procurement specification. A certificate of conformance is on flie.
A08 046 273 Submersible pumps are not part of Resolved by revsew of seism 6C Documentation Completed GlP's earthquake emperience date qualification documentation which shows Review
- base, that seismic design criteria consistent with our licensing basis was p6ft of the procurament specification. A certificate of conformance is on file.
A08 046 3C1 Suhmersible pumps are not part of Resolved by review of seismic Documentation Completed GlP's otrthquake experience date qualification documentation which shows Review base.
that seismic design criteria consistent with our licensing basis was part of the procurement specification, A certificate of conformance is on file.
A08 046 302 Submersible pumps are not part of Resolved by review of seismic Docurnentation Completed GIP's earthquake experience data qualification documentation which shows Review base.
that seismic design criteria consistent with our licensing basis was part of the procurement specification. A certif6cate of conformance is on file.
A09 145 392 Anchor bolts for these pumps do not Resolved by ana7l sisif actual Analysis Completed meet the least acceptable edge installation and review vendor analysis, destance (40). Also, the vertical shaft Anchotege and shaft stresses are length exceeds the mazimum length in acceptable, the boundeg spectrum caveat.
Page2 1
l
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,,,-rw..y.,.,,,,,-..,.--..,--,,-,r,--n
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- - ~,.. -.
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M*eolut6on of Equipment Outhore 11/17/97
)
i Cet ID Outhor Findina 1
- ._ C:__ _ : -
l Method l Resolution by j
A09 246 3g2 Anchor botte for those pumps do ret Resolved by onelysis of actual Analyele Completed meet the least acceptable edge installation and rev6ew vendor analysle.
I distance (40). Aieo, the vertical shaf t Anchorage and shaft stresses are length eaccede the monimum loneth in ecceptable, i
the boundeng spectrum cavest.
i A10 2RC 101 its floor response spectre Idemand)
Resolved by review vendor specif6catione Documentat6on Completed exceeds the capacity spectre of 1.5 wNch ceiled for 3g in the horisontal Review j
times the boundeng spectrum, dweetion and 2g in the vertical dvoction.
TNe capacity le grooter then the demand at tNo elevation.
I A10 2RC 10-2 The floor response spectra (demantil Resolved by review vendor specifications Documentation Completed onceeds the capeoity spectre of 1.5 wNch celled for 3g in the horisontal Review times the bounding spectrum, dwection and 2g in the vertical dwection.
This capacity le greater then the demand et tNo elevation.
A10 hC 101 The floor reponu specus (domand)
Resolved by revow vendor specificatione Documentation Completed suceeds the capacity spectre of 1.5 which celeed for 3g in the hortiontal Review I
times the bounding spectrum.
direction and 2g in the vertical direction.
TNe capacity le greater than the demand at tNo elevation.
I A10 RC to.2 The floor response spectra (demand)
Resolved by review vendor specificatione Documentation Completed suceeds the cepecity spectre of 1.5 which called for 3g in the hortrontal Review times the bouruhng spectrum.
direction and 2g in the vertical direction.
TNe capacity le grooter than the demand at tNe elevation.
All CV.39401 Contact with conduite could tweak the Conduit for valve will be rerouted to Modification U1 Outage May 9T solenoid top connection for these maintain 2' minimum clearance between valves.
conduite and velve.
Alt CV.39409 Contact w6th conduite could tweak the Air hne to solenoid volve will be terouted Modification U1 Ou: age May 99 solenoid top connection for these to maintain 2* mL.'. mum clearance valves.
between conduite and valve.
1 A12 CV.39421 Contact between the volve dieptvegm Conduit for volve will be rerouted to Modification U2 Outage Dec 98 housing and a 1' conduit could cause maintain 2' minimum clearance between chatter of the hmit switchee in the conduite and volve, solenoid volve I
A13 - CV 39405 The floor rnponse spectra (demand) Resolved by review of documentation Documentation Completed exceeds the capacity spectre of 1.5 wNch shows that solemic design criterle Review times the bounding spectrum, consistent with our licensing basis was part of the procurement specification.
Vendor Seismic Queltfication Hoport supporte capacity.
Page 3
.a.-..
m -,. - _ _ _. -,. _. -
Resolution of toutpmern Outleers 11/17/97 Cat I ID l
Outlier F6ndme Resoeulon Descrip*lon l
Method 1 Resolution by A13 CV.39417 The f6oor ressense spectre idemand)
Resolved by it' view of documentaten Documentation Completed exceeds the capacity spectra of 1.6 which shows that seismic design cratoria Review times the tound6ng spectrum, consistent with our licensing basis was part of the procurument spec.ification.
Vendor Seismie Quehfication Report supports capacity.
A13 CV 39419 The floor response spectre fdomand)
Resolved by rev6ew of documentation Documentation Completed exceeds the capacity spectra of 1.6 which shows that seismic design criteria Review 16mes the bounding spectrum, consistent with our licensing basis was part of the procurement specification.
Vendor Seismic Oushfication RepNt supports capsetty.
135281 The seismic demand exceeds the Resolved by analysis of the actual Analysis Completed A14 -
seismic capacity. Also, the anchorage installation. Naturs. frequency is > 10 details for these f ans covH not be Hs and capacity is great'st than demand.
determined.
Anchotoge is OK. Vendor Seismic Qualification Report supports rapacity.
A14 232 201 The seismic demn.eq encoeds the Resolved by analysis of the actual Analysis Completed seismic capacity. Also, the anchorage installation. Natural frequency is > 10 details for these f ans could twt be Hs arid capacity is greater than demand.
determined.
Anchorage is OK. Vendor Seismic Oushfication Report supports capacity.
A16 SV.J1498 This valve has a potential for Resolved by analysis of the actual Analysis Completed differential displacement botween the installation. Stresses in coppet tubing is wall and ductwork that supports the acceptable, volve's tubing.
A10 SV 37407 Seismic demand based on floor Resolved by review of documentation Documentation Cornpleted response spectra exceeds seismic which shows that seismic design critoria Review demand based on 1.5 times the consistent with our licensing basis was bounding spectra, part of tSe procurement specification. A certificate of conformance for 16g capacity la on file.
A17 074 031 Anchorage capacity of the FCU's Resolved by analysis of actual Analysis Completed could not be established.
installation. Rest /alnts determined to be rigid. Seismic fo#ces acceptable. No interaction from displa ement.
A17 074-032 Anchorage capacity of the FCU's Resolved by analysis of actual Atalysis Completed could not be estabbshed, installation. Rastraints determined to be rigid. Seismic forces acceptable. No interaction from displacement.
A17 07#033 Anchorage capacity of the FCU's Resolved by analysis of actual Analysis Completed could not be established.
instauation. Restraints determined to be rigid. Seismic forces acceptable. No 6nteraction from displacement.
Page 4 s
Resolution of [quipment Outhors 11/17/97 1
Cet 170 l
Outtier Finding l
Resolution Desertption l
Method l Resolution by j
A17 074-034 Anchorage capacity of the FCU's Resolved by onelysts of actual Analysis Completed could not be estabhshed.
irwtellation. Mestraints determined to be rigid. Seismic forces acceptable. No interaction from displacement, j
A18 174 061 Anchorage capactty of tte FCU's Resolved by analysis of actual Analysis Completed could not be established. Also, e installation. Original support and potential seismic interaction esists for anchorage calculations reviewed.
174 061 with a colhng mounted multi-Supports are adequate and relative tier conduit, displacement is less than observed gap.
A18 274 041 Anchorage capacity of the FCU's Resolved by analysis of actual Analysis Completed csuld not be estabhshed. Also, e installation. Original support and potential seismic interact 6on exists for anchorage calculations reviewed.
174-061 with a cwthng mounted multi-Supports are adequate and relative tier conduit, displacement is less than observed gap.
Alp 174 013 The floor response spectra (domand)
Resolved by analysis of actual Analysis Completed sacoeds the capacity spectra of 1.6 installatsen. Recently revised FCU yields times the bounding spectrum, lower natural frequency of 9.*a3Hr.
Vendor design report ft.t FCU shows capacity of 1.6g whch is larger than dem.and at 9 Hr.
A20 CD 34070 its floor response spectra (demand)
Resolved by analysis of actual Analysis Completed exceeds the capacity spectra of 1.6 6nstallation and review of vendor 16mes the bounding spectrum, supplied seismic quahfication reports using plant specific in-structure demand at 766',
A20 CD-34077 The floor response spectra Idemand)
Resolved by analysis of actual A nalysis Completed encoeds the capacity spectra of 1.6 installation and review of vendor times the bounding spectrum, suppled seismic quahficat6on reposts using plant specific in structure dernand at 766',
A20 CD 34078 ihe floor response spectra (demand)
Resolved by analysis of actual Analysis Completed onceeds the capacity spectra of 1.6 installation and review of vendor times the bounding spectrum, supphed seismic Qushfication reports using plant sr.acific in structure demand at 766',
A20 CD 34079 The floor response spectra (demand) nosolved by analysis of actual Analysis Completed onceeds the capacity spectre of 1.6 installation and review of vendor times the bounding sps,ctrum, supplied seismic quahfication tsports using plant specific irtstructure demand at 766*.
A20 CD-34084 The flodrosponse spectra (demand)
Resolved by analysis of actus)
Analysis Complated exceeds the capacity spectra of 1.6 installation and review of vendor times the boundsng spectrum, supphed seismic quahfication reports using plant specific in-structure demand at 76 6',
l Page 6
Resolution of Iovipment Outlers 11/17/97 cet I lo T
outii.r nndine no.oiotion Desertation I
usthod T nosolution by A20
'CD 34086 The floor respotise spectra (demand)
Resolved by analysis of actual Analyses Completed onceeds the capacJty spectre of 1.6 6nstallation and review of vendor times the bounding spectrum.
supplied seismic Cushfication repoits using plant specific in-structure demand at 766'.
A20 CD-34000 The floor response spectre teemand)
Resn4ed by analysis of actuat Analysis Completed naceeds the capocity spectra of 1.6 anstallation and review of vendor times the bounding spectrum.
eupplied seismic qualification reports using plant specific in-structure demand at 766*.
A20 CD 34087 The floor response spectra (demand)
Resolved by one'ysis of actual Analysis Completed escoeds the capacity spoetra of 1.5 installatloi. and review of vendor times the bounding spectrum, supplied seismic qualdiestion twports using plant specific irkstructura demar.d at 756'.
A21 076-011 These chillers have unconfined steel Plates to be installed around springs to Motheation Dec 97 isolator sprofigo in the base support, limet mo>ement.
A21 076-012 These chillers have unconfined steel Plates to be installed around spritigs to Modification Dec 97 isolator springs in the base support, limit rnovament.
A22 PNL 11 his panels base la elevated above the Resolved by analysis of the actual Analysis Completed
~
floor subjecting the anchorage to installation. Stresses in anchorage is bending stresses acceptable even "f th gap.
i A22 PNL 12 The panels bandelevated above the liesolved by analysis of the actual Analysis Completed floor subjecting the anchorage to installation. Stresses in anchorage is bending stresses acceptable even with gap.
A22 UNL 21 The panels base is elevated above the Fesolved by analysis of the actual Analysis Completed
~
floor subjecting the anchorage to installation. Stresses in anchorage is bending stresses acceptable even with gap.
A22 PNL 22 The perwis base is elevated above the Resolved by analysis of the actual Analysis Completed floor subjecting the anchorage to installation. Stresses in anchorage la beriding stresses acceptable even with gap.
i Page 6
. ~ ~ - -
.~
Rotonution of Equipment Outleers 11/1707 j
Cet ;!
ID Opener Pendina 1
C f L: F 2r l
Mothed I Resolutaen by A23A 21 SAT 1 The.
. D are over 10 years old.
Resolved by inoteketion of new better6es. Replecoment Completed l
t i
f A23B 11 BATT The bettery is over 10 yees old.
Resolved by review of vendor Documentation Completed
~
documentation on qualified service life of Review 20 years, i
I A24 12 BATT Foam pleetic spacers are not instehed Resolved by review of Emide Assembly Documentation Completed between bettery coi6e et locations instruction Section 58.10 paragraph 6, Rev6ew where there are cell clamp locations.
foam spacers are not required at cell clamp locations.
A24 22 BATT foom pleetic spacers are not installed Resolved by review of Emide Assembly Documentation Completed I
between bettery cells at locations instruction Section 58.10 peregraph 6, Rev6ew where there are cell cJamp locations.
foam specore are ret required at cell clamp lor.atione, I25 11 BATT CHO The cabinet besos are elevated above Resolved by new charger ir stellation.
Replacement Completed the floor subjecting the anchorage to Cap no tor $>r en leave.
bending stresses.
A25A 12 BATT CHGTte cabinet bases are elevated above Resolved by new charger installetion.
Replacement Completed the floor subjecting the anchorage to Gap no longer en lesue, bending stresses.
A258 22 BAT T CHGNie cabinet bases are elevated above Resolved by new charger installatiori.
Replacement & Completed the floor subjecting the encturage to Gap nc longer en leeue, Resolved door Documentation bending stresses. There are sleding counter weight by review of existing Review door counter weights which could
- onetysis, owing into 12/22 Bettery Charger eseociated panels.
A26 034 011 A local control panel mounted on the Angle son clips Eing installed around Modification Dec 97 DO ekid le supported on very fienible springs to limit movement.
(wobbly) steel springs.
A26 034 421 A local control panel mounted on the Angle iron clips being installed around ModificeWn Dec 97 D0 skid le supported on very flexible springs to limit movement.
twobbly) steel springs.
Page 7
Resolution cf Louipment Outhore 11/17/97 Cet i
10 1
Outlier f6ndma l
Resolution Desertation klethod 1 Resolution by A27 14MFi Aluminum diff ussets in the control iflem6ble cord wp hooks will be installed Work Regwst Dec 97 room colhng pose a personnel hasard, to secure diffusers to collm0 9 tid.
A27 1NR3 Aluminum diffussers in the control flexible cord eth hooks well be 6nstalled Work Request Dec 97 i
room coihng (Mw a personnel hatard.
to secure diffusers to ceiling Or6d-A27 1M4 Aluminum ditfussers in the cont'ol Flexible cord with hooks will be installed Work R6 quest Dec 97 room ceiling pose a persormel hasard, to secure diffusers to colling grid, dW 2NR3 Asuminuto ddiussets in the control flexible cord with hooks wiA be installed Work Request Dec 97 room ceiling pose a personnel hatard.
to secure diffusers to colkn9 DrId.
A27 2NR4 Aluminum diffussers in the control flexible cord with hooks will be installed Work Request Dec 97 room celkng pose e personnel hatard, to secure diffusers to coikng grid.
A27 A
Alum 6num diffussers in the control Flexible cord with hooks will be installed Work Nguest Dec 97 room colhng pose a personnel harard, to sacute diffusers to celbnD grid.
[27 D1 Aluminum diffussers in the control flexible cord with hooks will be installed Work Roquest Dec 97
~
room colhng pose a personnel haterd, to secco diffusers to ceiling grid.
A27 D-2 Aluminum diffussers in the control flemible cord with fooks will be installed Work Reques[ Dec 97 room conhng pose a personnel hazard.
to secure ddfusers to ceiling grid.
A27 C1 Aluminum diffussers in the control flexible cord with hooks will be installed Work Request Dec 97 room ceihn0 pose e personnel herord, to secure diffusers to ceilin9 Orid.
l Page 8 l
Resolution of fou4 ment Outlawa 11/1Ef 7 Cet ID l
~ Oveller Phdha I
t f_^_-CI___._
Moshe4 I nei aiution by A27 C2 Alummum deffuseere in the control
~Flemible cord with hooks we be insteI6ed Wart stoquest Dec 97 rsom oeiling pose a personnel harerd.
to aooure Gtfunera to ceiling grid.
A27 D1 Alurninum $ffuseers en the control flexible cord with hooks we be installed Work Request Dec 97 rcom colling pose a personnel harerd.
to 6ecura detfusere to esiling prid.
I A27
'pI2 Alumirum diffuenote in the control Flexible cord with hooks will be installed Work Request Dec 97 l
room coni.ig pue a personnel hasard.
to secure diffusers to ceiling grid.
'27_
i.I Anurr*m.em his%As An the control Flexible cord with hooks will be installed Work Request Dec 97 A
Wrn toturg f%io a tiersonnet inasard, to teoute d6ffusers to ceiling grid.
A27 E2 Aluminum diffuseers in the control Flexible cord with hooks will be installed Work Request Dec 97 roorn calling pots a personnel hasard, to secure diffusers to ceiling grid.
27 F1 Alur$6nurr fittussers in the control Flexible cord with hooks will be installed Work Roquest Dec 97 room cell eg pose a personnel hazard, to secure diffusers to ceiling grid.
A27 sI Aletninum dif fussers in the control Flexible cord with hooks will be installed Work Request Dec 97 room ceiling pnoe a personnel hazard.
to secure diffusers to ceiling grid.
A27 01 Alum 6num dif fuseers in the control Flexible cord with hooks will be installed Work Roguest Dec 97 room ceiling pose a personnel hazard, to.ecure diffusers to ceiling grid.
A28 D6/HTI' h computer tehle with a loose A cabinet will be installed to house this Modification Dec 97 computer CRT and printer alta equipment to preclude interaction, adjacent to the RTU cabinets presenting a swamic interaction hatard.
=
hae 9
Resolution of touipnwnt Outlers 11/17/97 cet i
in I
outner rintsna 1
me.oiution Dese tption I
wethod l Resolution by A28 D6HLTU A computer tatste with a loose A cotunet will be installed to house this Modifgetion Dec 97 computer CRT and printer sits equipment to preclude interaction.
adjacent to the RTU cabinets I
presenting a seismic interaction
- hetard, 1
)
'T '1 053 221
'Outhor. The flealbility of buried piping Resolved by evaluation of bur 6ed piping Analysis Completed could not be determined from between tank and AUX Buildeg.
i available documentation Stresses due to seismic effects are 1
acceptable.
T1 053-223 Outhor. The flexibihty of butted piping Resolved by evaluation of buned piping Analysis Completeri could not be determined from betwoon tank and AUX Duilding.
available documentation Stresses due to seismic effects are acceptable.
T1 063-261 Outhor. The flexibility of buried piping Resolved by evaluation of buried piping Analysis Completed could not be determined from between tank and AUX Building.
evallable documentation Stresses due to seismic effects are acceptable.
T1 063 262 Outher. The flexibihty of buried piping Resolved by evaluation of buried piping Analysis Completed could not be determined from betwoon tank and AUX Duilding.
evallable documentadon Stresses due to seismic effects are acceptable.
12 135-021 Outhor. The stress in the supports Resolved by review of existing analysis.
Documentatic Completed enceed GIP allowables Review T2 235 131 Outhor. The stress in the supports Resolved by review of e dsting analysis.
Documentation Completed exceed GIP allowables Review T3 136;101 Outher. This HX is an outher because 3eephed by analysis of ineximum Analysis Completed at is not secured to the pedestals noir.mic acceleration compared to (mounting cradles are secured to the restraining forces due to the coefficient pedestals but HX is not attached to of foetion. Low level of acceleration will the cradles). Further both cradlee have not r.vercome friction.
Slotted mounting holes which furthet makes this comp, an outlet.
13 236 081 Outhor. This HX is an outhor because Hosolved by analysis of maximum Analysis Completed it is not secured to the pedestals seismic acceleration compared to (mounting cradles are secured to tie restraining forces due to the coefficient pedestals but '4X is not attached tu of friction. Low level of acceleration will the cradles). Further both crsses have not overcorn friction, slotted mounting holes which further makee this comp an outlier.
Page 10
.. ~.. _. _. _ _ -.. _ _. _. _. _ _ _
i f.
Resolut6on tf Igulpment Outlers 11/17/97 Outhor Finstna l
":- ';tr Ex;ttr 1
Method l Roeolution by Cet l
ID l
T4 163 011 Outher. The tod le on outier due to Resolved by onelyses. Seem6c Anotyo6s Ccmpleted; the slotting of holes in both support accelerotion le lose then one half of Re torque
(
plates fr6ctionaltenietence. However as en U1 Outopo Dec 97 i
entre moteure of conservatism, ou 4 bolts on any one soddie will be to.
torqued.
i 14 263-011 Outler. The tank is en outteer due to Mesolved by entlysis. Seismic Anotyo6s Completed the slotting of holet in both support accewretion is less then one half of plates fr6ctional resistenne. However as en entre inopours of consc<vetism, en 4 botte on any one enddle will be te torquod.
j j
Treys Ops Lounge Outler. Cetdo Troy interaction with Guard to be inste16ed around the cable Modification Dec 97 Inorcise Equipment tray arW conduits to protect tre components, r
b L
6 e
f i
i 6
i B
a Page 11 e
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-,-,,-,,,.,-n
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s
94 ATTACHMENT 3 RELAY OUTLIER RESOLUTIONS
Resolution of Relay Outliers 11/17/97 ID l
Outlier findne i
Resolution Description l Method l Remorution by Cet 401 ILC 4278-X MOST CONSERVATIVE Resolved by analysis. Cabinet 1 AMRI has been re-Analysis Completed CAPACITY ASSIGNED FROM analysed for in cab not demand. New demand is now GERS GERS SHAPE.
less than relay capetJty.
401 ILC 4288 X MOST CONSERi/ATIVE Resolved by analysis. Cabinet 1 AMR1 has been re.
Analysis Completed CAPACITY ASSIGNED FROM analysed for in cabinet demand. New demand is now GERS. GERS SHAPE.
less than relay capacity.
R01 ILC 4280 X MOST CONSLRVATIVE Resolved by analysis Cabinet 1 AMR1 has been re-Analysis Completed CAPACITY ASSIGNED FROM analytod for in c6 binet demand. New demand is now GERS. GERS SHAPE.
less than relay capacity.
21 1PC 431E X MOST CONSERVATIVE Resolved by analysis. Cabinet 1 AMRI has been re-Analysis Completed CAPACITY AS$1GNED FROM analysed for in cabinet demand. New demand is now GERS. GERS ENAPE.
less than relay capacity.
IDI 2LC-4278 X MOST CONSERVATIVE Resolved by analysis. Cabinet 2AMR1 has been re-Analysis Completed CAPACITY ASSIGNED FROM analysed for in cabmet demand. New demand is now GERS. GERS SHAPE.
less than teley capacity.
801 2LC 4280 X Mt.ST CONSERVAT.VE Resolved by onelysis. Cabinet 2AMR1 has been to.
Analysis Completed CAPACITY ASSIGNED FROM analyzed for in cabinet demand. New demand is now GERS. GERS SHAPE.
less than relay capacity.
R01 2LC 4280 X MOST CONSERVATIVE Resolved by analysis. Cabinet 2 AMR1 has Deen re-Analysis Completed CAPACITY ASSIGNED FROM analysed for in cabinet demand. New demand is now GERS GERS SHAPE.
less than relay capacity.
R01 2PC 431E X MOST CONSERVATIVE Resolved by analysis. Cabinet 2AMRI has been to.
Analysis Completed CAPACITY ASSIGNED FROM analysed for in cabinet demand. New demand is riow GERS. GERS SHAPE.
less than relay capacity.
IIO2 26X/1120-NO APPLICADLE GERS, This relay is associated with the control room chiller. Procedure Dec 97 1A The resolution for these outliers is to have Revision Operations restart the Control Room chillers after the seismic event if necessary. Procedures to be revised.
R02 26X/1120-NO APPLICABLE GERS.
This relay is associated with the control room chiller. Procedure Dec 97 1C The resolution for these outliers la to have Revision Operations restert the Control Room chillers after the seismic event if necessary. Procedures to b3 revised.
R02 4X/112G 1 NO APPLICABLE GERS.
This relay is associated with the control room challer. Procedure Dec 97 The resolution for these outliers is to have Revision Operations restart the Control Room chillers after the seismic event if necessary. Procedures to be revised.
R02 03X/11201 NO APPLICABLE GERS.
Th6s relay is associated with the control room chiller. Procedure Dec 97 The resolution for these outliers is to have Revis'on Operations restart the Control Room chillers after the seismic event if necessary. Procedures to be revised.
32 26X/1220-NO APPLICABLE GERS.
This relay is assoc 6ated with the control room chiller. Procedure Dec 97 1A The resolution for these outliers is to have Revision Operations restart the Control Room chillers af ter the seismic event if necessary. Procedures to be revised.
Page 1
Resolution of Relay Outliers 11/17/97 no. knion Description I usihod
! R.sosution by c.
E
~io I
outleet nnana hC2 26X/1220-NO APPLICABLE GERS.
itus relay is assooseted with the control room CNiler, Procedure De J 97 1C The resolution for stne outhers is to have Revision Operations restart the Control Room chillers after the seismic event if necessary. Procedures to be revised.
R02 4X/12201 NO APPLICABLE GERS.
This relay is associated with the control room cNiler.
Procedure Dec 97 The resolution for these outliers is to have Revitiion Operations restart the Control Rom chillers after the seismic event if necessary. Procedures to be revised.
R02 63X/12201 NO APPLICABLE GE9S.
TNs relay is associated with the control room cNiler.
Procedues Dec 97 The resolut6on for these outhors is to have Revision Operations testart the Control Room chillers af ter the seismic event of necessary. Pacedures to be revised.
R03~
67X/D1 MODEL NUMBER UNAVAILABLE Resolved by similartty analysis to 4U3 and 4US.
Analysis Completed FOR RELAY, THEREFORE OUTLi[R CLAS$1FICATION AS$1GNED.
504 86/D1 NO APPLICABLE GERS.
Resolved by s6milarity enelysis of HEAC3 to HEA61.
Analysis Completed Rob 431X/D1 ANSI SHAPE.
Resolved by analysis. Cabinet 55410 has been to-Analysis Completed analyzed for in cabinet demand. Now demand is now less than relay capacity.
Rob 43tXX/D1 ANSI SHAPE.
Resolved by analysis. Cabinet f,5410 has been re-Analysis Completed analyzed for in cabinet demand. New demand is now less than relay capacity.
805 431XXX/D1 ANSI SHAPE, Resolved by analysis. Cabinet 55410 has been to-Analysis Completed analyzed for in cabinet demand. New demand is now less than relay capacity.
R03 67X/02 MODEL NUMBER UNAVAILABLE Resolved by similanty analysis to 4U3 and 4U8.
Analysis Completed FOR RELAY, THEREFORE OUTLIER CLASSIFICATION ASSIGNED.
R04 86/D2 NO APPLICABLE GERS.
hasolved by similarity analysis of HEA63 to HEA61.
Analysis Completed R02 5)30303 NO APPLICABLE GERS.
This relay is associated with the control room CNiler.
Procedure Dec 97 The resolution for these outhers is to have Revision Operations restart the Control Room cNiters after the seismic event if necessary. Prc.cedures to be revised.
R02 5130304 NO APPLICABLE GERS.
TNs relay is associated with the control room chiller. Procedure Dec 97 The resolution for these otroliers is to have Revision Operat6ons testart the Control Room chillers af ter the seismic event if necessary Procedures to be revised.
802 5730305 NO APPLICABLE GERS.
This relay is associated with the control room cNiler.
Procedure Dec 97 The resolution for these outliers is to have Revision Operations testart the Control Room cNilers af ter the seismic event if necessary. P;ocedures to be revised.
Page 2
Resolutsoa of Relay Outhors 11/17/97 Cet 1
ID l
Outtler Finding l
Resolution Description 1 Method l Resolution by H02 6730316 NO APPLICABLE GERS.
TNs relay 4 associated wrth the control room cheller. Procedure Dec 97 The resolut,m for these outliers is to have Revision Operations restart the Control Room chillers after the selsmic event if riocessary. Procedures to be revised.
R02 6730403 NO APPUCABLE GERS.
Thss relay is associated with the control room cNiter.
Procedure Dec 97 The resolution for those outhors is to have Revision Operations restart the Control Room cNilers af ter the noismic event if necessary. Procedures to be revised.
' 02 6730404 NO APPLICABLE GERS.
This relay is associated with the control room chiller.
Procedure Dec 97 2
The resolution for these outleets is to have Revision Operations restart the Control Room cNilers af ter the seismic event if necessary. Procedures to be revised.
R02 6730406 NO APPLICABLE GERS.
This relay is associated with the control room cNfler.
Procedure Dec 97 The resolution for these outliers is to have Revision Operations resta.t the Control Room cNilers after the seismic event if necessary. Procedures to be revised.
H02 6730411 NO APPLICABLE GERS.
Ttus relay is associated with the control room chiller. Procedure Dec 97 The resolution for these outliers is to have Revision Operations restart tt e Control Room chillets after the seismic event if necessary. Procedures to be revised.
R03 16X/12CLP NO APPLICABLE GERS.
Resolved by sim:arity analysis to 4U3 and 4UB.
Analysis Completed Penalarm has been replaced by Clark 4U4.
R03 16X/22CLP NO APPLICABLE GERS.
Resolved by similarity analysis to 4U3 and 4U8.
Analysis Completed Penalarm has been replaced by Clark 4U4.
203 8BI112C NO APPLICABLE GERS.
Resolved by similarity analysis to 4U3 and 4US.
Analysis Completed ABB RXMS1 replaced by Clark 4U4.
R03 86/122C NO APPLICARLE GERS.
Resolved by similarity analysis to 4U3 and 4US.
Analysis Completed
~
ABB RXMS1 replaced by Clark 4U4.
203 4TDG1 16 NO APPLICABLE GERS.
Resolved by similarity analysis to 4U3 and 4US.
Analysis Completed R06 60G/16 2 THIS IS A LOW RUGGEDNESS Replace with ABB Type 60H solid state relays Modite ation U1 Outage Dec 97 RELAY PER EPRI NP.7148-SL, APPENDIX E.
R06 60G/1fb3 THIS IS A LOW HUGGEDNESS Replace with ABB Type 60H solid state relays.
Modification U1 Outage Dec 97 RELAY PER EPRI NP-7148 SL.
APPENDIX E.
R06 600/16-9 THIS IS A LOW RUGGEDNESS Replace with ABB Type 60H solid state relays,
' Modification U1 Outage Dec 97 RELAY PER EPRI NP 7148 SL.
APPENDIX E.
Page 3
., =.-
Rwsolution of Retey Outliera 11/17/97 Cet l ID l
Outlier Finding i
Resolution Description l Method I Resolution by ROF 1X/111J 1 NO APPLICADLE GERS.
Resolved by sumlarrty analysis of KAP 11 A0 to KAP. Analysis Completed 11AY.
ROF IX/121J 1 NO APPLICABLE GERS.
Resolval by similartty analysis of KAP 11 A0 to KAP. Analysis Completed 11AY.
R08 BKR 1120-6 MODEL NUMBER UNAVAILABLE MV 32016 is being repowered by a motor starter Modification U1 Outage Dec 97 FOR MOTOR STARTER, located within 40' above grad whose capacity THEREFORE OUTLl[R exceeds demand.
CLASSIFICATION IS ASSIGNED.
208 BKR 2120 3 MODEL NUMBER UNAVAILABLIMV 32019 has been reps - ored by a motor starter Modification completed
~
FOR MOTOR STARTE81, located within 40' at sve grade whose capacity THEREFORE OUTLIER exceeds demand.
CLASSIFICATION ASSIGNED.
ROS BKR 1220-0 MODEL NUMBER UNAVAILABLE MV.32017 is be6ng repowered by a motor starter Modification VI Outago Dec 97 FOR MOTOR STARTER, located within 40' above grade whose capacity THEREFORE OUTLt[R exceeds demand.
CLASSIFICATION ASSIGNED.
' 08 PER 222G 3 MODEL NUMDER UNAVAILABLE MV 32020 has been repowered by a motor starter Modification Completed 2
FOR MOTOR STARTER, located within 40' above grade whose capacity
.8 THEREFORE OUTLtER exceeds demand.
CLASSIFICATION ASSIGNED.
R07 1X/211J 1 NO APPLICABLE GERS.
Reso'ved by similarity analysis of KAP.11 A0 to KAP-Analysis Completed 11AY.
207 IX/221J.1 NO APPLICABLE GERS.
Resolved by similarity analysis of KAP 11 AC to KAP-Analysis Completed 11AY.
iiO1 LPT/31998 ANSI SHAPE.
Resolved bw analysis TB A1640 has been to.
Analysis Completed analyzed fur in cabinet demand, New demand is now less than relay capacity.
R01 LPT/31999 ANSI SHAPE.
Resolved by analysis. TB 220g has been re analyzed Analysis Completed for in cabinet demand after instalkng shims to eliminate gap at anchorage. New demand is now less than relay capacity, i
l Page 4 i
i 1
ATTACHMENT 4 ANCHOR SOFTWARE EVALUATIONS i
MCC 2K1 145-201 i
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Prairie Island Nuclear t::nerating Plant GIP R:;v 2, Corrected,2/14/92 t
SCREENING EVALUATION WORK SHEET (SEWS)
Status: Yes Sheet 1 of 9 -
ID : MCC 2K1 ( Rev. 0 )
l Class : 1. Motor Control Centers Description : MOTOR CONTROL CENTER 2K BUS 1 Building: AUX Floor El. : 095.00 Room, Row / Col : G.2/123 NEAR RHR PIT Manufacturer, Model, Etc. -
EEISMIC CAPACITY VS DEMAND 1.
Elevation where equipment receives seismic input 695.00
'L --
Elevation of seismic :nput below about 40' from grade (gtade v 695.00)
N@
3.
Equipment has fundamental frequency soove about 8 Hz (est. frequency = 5.00)
N/A 4-Capacity based on:
1.50
- Bot.nding Spectrum 5.
Demand based on:
1.00
- Conservative Desigo Floor Response Spectra 2.000 n
~
i1 0
l
't LIN
/
\\
/
\\
,/
\\.
j
,.../
- ~ ~ ~ -........,....
0.000
- 1. vf1,,i s i iiiii!
i ie e
i i i iiii 0.20 LOG Hz 100.00 Cepacity.,. Demand File Record Capacity H \\GtP\\ GIP \\ spectra des Labellpounding Spectrum -
Demand 1 HAGIPTPROJ0040\\ spectra det -
DUILDINGIRB/AB/iDIELEVATION1695 OOIDIRECTIONiHORIZONTA L'.'4 ASS POINTSl20. 20A. 32. 42l RADIAL DISTl100 Demand 2 H \\61P\\PROJ0040\\ spectra des DUILDINGlRB/AD/TBIELEVATIONI695 0C;DIRECTIONIHORIZONTA LIMASS POINTSl20,20A; 32. 42iRADIAL DISTl100 Does capacity exceed demand?
Yes i
i i
m
Prairie I; land Nuclear Generating Plant GIP Rrv 2, Corrected,2/14/92 SCREENING EVALUATION WORK SHEET (SEWS)
Status: Yes Sheet 2 of 9 JD : MCC 2K1 ( Rev. 0 )
l Class : 1. Motor Control Centers Description : MOTOR CONTROL CENTER 2K BUS 1 Building: AUX Floor El. : 695.00 Room, Row / Col: G.2/12.2 NEAR RHR PIT Manufacturer, Model, Etc.
- CAVEATS - BOUNDING SPECTRUM MCC/BS Caveat 1 Earthquake Experience Data Base.
-Yes MCC/BS Caveat 2 Rating of 600 V or Less.
Yes MCC/BS Caveat 3 Adjacent Cabinets Bolted Together.
Yes MCC/BS Caveat 4 - Attached Weight of 100 Pounds or Less.
Yes MCC/BS Caveat 5 - Externally Attached items Rigidly Anchored.
Yes MCC/BS Caveat 6 - General Configuration Similar to NEMA Standards.
Yes MCC/BS Caveat 7 - Cutouts Not Large.
Yes MCC/BS Caveat 8 - Doors / Buckets Secured.
Yes MCC/BS Caveat 9 - Natural Frequency Relative to 8 Hz Limit Considered.
Yes JJCC/BS Caveat 10- Adequate Anchorage.
Yes MCC/BS Caveat 11 - Potential Chatter of Essential Relays Evaluated.
Yc?
MCC/BS Caveat 12 - No Other Concerns Yes is the intent of all the caveats met for Bouncing Spectrum?
Yes ANCHORAGE
- 1. The sizes and locations of anchors have been determined.
Yes
- 2. Appropriate equipment charactenstics have been determined (mass, CG, natural freq.,
Yes damping, center of rotation).
- 3. The type of anchorage is covered by the GIP.
Yes
- 4. The adequacy of the anchorage installation has been evaluated (weld quality and lengtn, Yes nuts and washers, expansion anchor tightness, etc.)
- 5. Factors affecting anchorage capacity or margin of safety have been considered: embedment Yes length, anchor spacing, free-edge distance, concrete strength / condition, and concrete cracking.
- 6. For bo;ted anchorages, any gaps under the base are less than 1/4.
Yes
- 7. Factors affecting essential relays have been considered: gaps under the base, capacity Yes reduction for expansion anchors.
- 8. The base has adequate stiffness and the effect of prying action on anchors has been Yes considered.
- 9. The strength of the equipment base and the load path to the CG is adequate.
Yes
- 10. The adequacy of embedded steel, grout pads or large concrete pads have been evaluated.
Yes
- 11. The anchorage capacity exceeds the demand.
Yes Are anchorage requirements met?
Y.es
Prairie Island Nuclear Genercting Plant GIP Rev 2, Corrected,2/14/92 SCREENING EVALUATION WORK SHEET.' SEWS)
Status: Yes Sheet 3 of 9 10 : MCC 2K1 ( Rev. 0 )
l Class : 1. Motor Controi Centers Der,cription : MOTOR CONTROL CENTER 2K BUS 1 Building : AUX Floor El. : 695.00 Room, Row / Col: G.2/12.2 NEAR RHR PIT
~
Manufacturer, Model, Etc. :
INTERACTION EFFECTS
- 1. Soft targets are free from impact by nearby equipment or ctructures.
Yes
- 2. If the equipme71 contains sensitive relays, it is free from all impact by nearby equipment or Yes structures.
- 3. Attached lines have adequate flexibility.
Yes
- 4. Overhead equipment or distribution systems are not likely to collapse.
Yes
- 5. No other adverse concerns were found.
Yes is equipment free of interaction effects?
Yes IS EQUlEMENLSEISMICALLY ADEQUATE 2 Yss COMMENIS SRT: F. Stille (S&A) and G. Gore (NSP)- 7/27/95.
REF: Pioneer Dwg. NF-39203 Rev. AB, NF 38298-8 Rev. T and NF-38298-9 Rev AB Capacity vs. Demand The seismic demand exceeds the capacity at a low frequency (approx. 3 Hz), but it is acceptable because the demand is enveloped at and above the estimated frequency (5 Hz).
Anchorage:
MCC 2K' 's a 7 unit floor mounted assembly 90" high,140" wide and 20" deep. The MCC is anchored by 14 - 1/2" Phillip shell(ref.), one bolt centered in the front and back of each unit, spaced 15.75" apart. All of the bolt nuts were tightness checked and judged 0.K.
The anchorage analysis consider the anchorage capacity of 2 units as being representative of the 7 unit MCC line. Also, the analysis uses the uiP typical maximum mass of 800 lbs per cabinet for MCCs (GlP table C.1-1).
Evaluated by:
Gerry Gore Date:
Frank Stille
Attachment:
Pictures
- Attachmont: ANCHOR Report
1 Prcirls Isl:nd Nuclect Gsnsrating Plant GlP Rev 2, Corrected,2/14/92 SCREENING EVALUATION WORK SHEET (SEWS)
Status: Yes Sheet 4 of 9 ID : MCC 2K1 ( Rev. 0 )
l Class : 1. Motor Control Centers Description : MOTOR CONTROL CENTER 2K BUS 1 Building : AUX Floor El. : 695.00 Room, Row / Col: G.2/12.2 NEAR RHR PIT Manufacturer, Model, Etc.
l l
ElGIURES l
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i MCC 2K1 i
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J
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,w,,--rwv-,,--n-ww w--,,,,-,--m-w-n,,-
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- Prairie Island Nuclear Generating Plant GIP R;y 2, Corrected,2/14/92 SCREENING EVALUATION WORK SHEET (SEWS)
Status: Yes -
Sheet 5 of 9 ID : MCC 2K,1 ( Rev. 0 )
l Class : 1. Motor Control Centers Desenption : MOTOR CONTROL CENTER 2K BUS 1 Building : AUX Floor El. : 695.00 Room, Row / Col : G.2/12.2 NEAR -
Manufacturer, Model, E,tc. :
ANCHOR Repor Earthquake; Response Spectrum : Instructure Conservative Frequency : User-5.00 Percent Damping : User-5.00
(-
Spectral Values :
Direction Acceleration (g's)
North - South 0.432 East West 0.432 Vertical 0.132 Angle (N-S Direction makes with the X Axis) : 0.00 Combination Criteria : SRSS Walehtal Number of Weights : 2 No Weight X
Y Z
1-
- 800.00 10.000 10.000 45.000 2
800.00 30.000 10.000 45.000 EDEC.tt; Number of Extemal Forces : 0 Moments; Number of Extemal Moments : 0 Allowables; Anchot; Number of Anchor types : 1 Tension Shear Ultimate Ultimate inter inter Saf No.
Dia Manufact Product Tension Shear Coeff Coeff Fact 1
1/2 Phillips Self Drilling 2290.00 2380.00 1.00 0.30 1.00 (S)
Concrete :
Ultimate Stress : 3000.00 psi..
Reduction Factor : 0.85 Weld:
Prairie 1:l:;nd Nucle:r U:nerating Pl:nt GlP R;v 2, Corre::ted,2/14/92 SCREENING EVALUATION WORK SHEET (SEWS)
Status: Yes l
Sheet 6 of 9 l
lD : MCC 2K1 ( Rev. 0 )
l Class : 1. Motor Control Centers Description : MOTOR CONTROL CENTER 2K BUS 1 Building : AUX Floor El. : 695.00 Room, Row / Col: G.2/12.2 NEAR RHR PIT Manufacturer, Model, Etc.
Allowable Stress : 30600 psi.
Surfacen.;
Number of Surfaces : 1 Surface Orientation Direction Direction Direction Comp Comp Comp No Nx Ny Nz 1
0.000 0.000 1.000 Anchor Pattem for Surface # 1 m
X Legend for Anchor Patterns Anchor Bolts :
Concrete Lines :
[_ ]
Concrete Points :
]
Weld Lines :
090mtityl Anchor :
Number of Anchors : 4
Prairie I: land Nuclear Generating Plant GIP R;v 2, Corrected,2/14/92
. SCREENING EVALUATION WORK SHEET (SEWS) '
Status: Yes Sheet 7 of 9 ID : MCC 2K1 ( Rev. 0 ) -
l Class : 1. Motor Control Centers Desenption : MOTOR CONTROL CENTER 2K BUS 1 Building ; AUX Floor El. : 695.00 Room, Row / Col : G.2/12.2 NEAR RHR PIT Manufacturer, Model, Etc.
Anch X
Y Z
Surf No.
id Coord Coord Coord Id 1
1 10.000 2.125 0.000 1
2-1 30.000 2.125 0.000 1
3 1
30.000 17.875 0.000 1
4 1
10.000 17.875 0.000 1
CDDClete Lines;
- of elements per line : 5 Number of Concrete Lines : 2 Start Start Sta.1 End End End S'
Line No X-Coord Y Coord 2-Coord X-Coord Y Coord Z-Coord Id Width 1
0.000 1.500 0.000 40.000 1.500 0.000 1
3 000 2
0.000 18.500 0.000 40.000 18.500 0.000 1
3.000 Concrete Point Number of Concrete Points : 0 Weld Lines :
- of elements per line : 4 Number of Weld Lines : 0 Detennination_omeduction Factoft.;
Reduction Factor input for Anchor # 1 Adequately Installed : Yes Embedment Length : ( 2.03 in. Min Reqd to achieve full capacity) := 2.03 in.
Gap at Threaoed Anchor : 0.00 in.
Edge Distance Edge 1 : 3.13 in.
Crack Size : 0.000 in. - Cracks Affect <= 50% Bolts Essential Relays in Cabinet : Yes Adequate Equipment Base Strength and Structural Load Path : Yes Embedmont Steel and Pads Adequately installed : Yes Reduction Factor input for Anchor # 2 Adequately Installed : Yes Embedment Length : ( 2.03 in. Min Reqd. to achieve full capacity) := 2.03 in.
Gap at Threaded Anchor : 0.00 in.-
Edge Distance - Edge 1 ; 3.13 in.
Crack Size : 0.000 in. - Cracks Affect <= 50% Bolts I
Essential Relays in Cabinet : Yes Adequate E_quipment Base Strength and Structural Load Path : Yes 4
o Prairie 1: land Nuclear enerating Plant GIP R::V 2, Corrected,2/14/92 SCREENING EVALUATION WORK SHEET (SEWS)
Status: Yes Sheet 8 of 9 10 : MCC 2K1 ( Revi 0 )
l Class : 1. Motor Control Centers Desenption : MOTOR CONTROL CENTER 2K BUS 1 Building : AUX Floor El. : 695.00 Room, Row / Col : G.2/12.2 NEAR RHR PIT Manufacturer, Model, Etc.
Embedment Steel and Pads Adequately Installed : Yes Reduction Factor input for Anchor # 3 Adequately Installed : Yes Embedment Length : ( 2.03 in. Min Reqd. to achieve full capacity) := 2.03 in.
Gap at Threaded Anchor : 0.00 in.
Edge Distance Edge 1 : 3.13 in.
Crack Size : 0.000 in. - Cracks Affect <= 50% Bolts Essential Relays in Cabinet : Yes Adequate Equipment Base Strength and Structural Load Path : Yes Embedment Steel and Pads Adequately installed : Yes
- Reduction Factor input for Anchor # 4
- Adequately Installed : Yes
- Embedment Length : ( 2.03 in. Min Reqd. to achieve full capacity) := 2.03 in.
Gap at Threaded Anchor ; 0.00 in.
Edge Distance - Edge 1 :. 3.13 in.
Crack Size : 0.000 in. - Cracks Affect <= 50% Bolts Essential Relays in Cabinet : Yes Adequate Equipment Base Strength and Structural Load Path : Yes Embedment Steel and Pads Adequately Installed : Yes Reduction Factors Data Current : Yes Anc Palt/
Pallr/
No ld Vall Valir RT RN RL RG RS RE RF RC RR RP RB RM 1
1 805 08 N/A 1.00 1.00 1 00 1.00 1.00 0 63 0 75 1.00 0 75 1.00 1.00 1.00 837.88 N/A 1,00' 1.00 1.00 1.00 1.00 0 49 0 95 1.00 0 75 1.00 1.00 1.00 2
1 805 08 N/A 1.00 1 00 1 00 1 00 1.00 0.63 0 75 1.00 0.75 1.00 1.00 1.00 83? 88 N/A 1 00 1.00 1.00 1.00 1.00 0 49 0 95 1.00 0.75 1 00 1.00 1.00 3
1 805.08 N/A 1 00 1.00 1.00 1.00 1 00 0 63 0.75 1.00 0.?$
1.00 1 00 1.00 83? 88 N/A 1.00 1.00 1 00 1.00 1 00 0 49 0 95 1.00 0.75 1.00 1.00 1.00 4
1 805 08 N/A 1 00 1 00 1 00 1.00 1 00 0 63 0.75 1.00 0.75 1.00 1 00 1.00 837.88 N/A 1.00 1.00 1 00 1 00 1.00 0 49 0 95 1.00 0.75 1.00 1.00 1.00 Legend; N/A
= Not Applicable Pall
= Allowable Pullwithout Reduced Inspection Vall
= Allowable Shear without Reduced Inspection Palir
= Allowable Pull with Reduced inspection Vallr a Allowable Shear with Reduced Inspection
= Outlier X
= Reduction Factor Not Used RT-
= Reduction Factor for Type of Anchorage RN
= Reduction Factor for installation Adequacy L.
RL
= Reduction Factor for Embedment l'
oL Prairie Island Nuclear Generating Plant GIP R;v 2, Corrected,2/14/92 _
SCREENING EVALUATION WORK SHEET (SEWS)
Status: Yes Shet t 9 of 9 ID : MCC 2K1 ( Rev. 0 )
l Class : 1. Motor Control Centers Desenpton : MOTOR CONTROL CENTER 2K BUS 1 Building: AUX Floor El. : 695.00 -
Room, Row / Col : G.2/12.2 NEAR -
RHR PIT Manufacturer, Model, Etc..
RG-
= Reduction Factor for Gap at Anchors RS
= Reduction Factor for Spacing RE
= Reduction Factor for Edge Distance RF
= Reduction Factor for Concrete Strength RC
= Reduction Factor for Concrete Cracks RR.
= Reduction Factor for Essential Relays RP
= Reduction Factor for Base Stiffness and Prying Action RB
= Reduction Factor for Base Strength and Load Path RM
= Reduction Factor for Embed. Steel and Pads Analysis.Resultu Analysis Performed : Yes Type of Analysis : Regular Spectral Accelerations (G's)
No NS E-W Vertical Safety Factor j
1 0.432 0.173 0.053 2.187 2
-0.432
-0.173
-0.053 2.349 3
-0.432 0.173 0.053 2.187 I
4 0.432
-0.173
-0.053 2.349 5
0.432
--0.173 0.053 2.187 6
-0.432 0.173
-0.053 2.349 7
0.432 0.173 0.053 2.349 8
0.432
-0.173 0.053 2.187 9
0.173 0.432 0.053 1.288 10
-0.173
-0.432
-0.053 1.348 11 0.173
-0.432 0.053 1.288 12
-0.173 0.432
-0.053 1.348 13
-0.173 0.432 0.053 1.288 14 0.173
-0.432
-0.053 1.348 15 0.173 0,432
-0.053 1.348 16
-0.173 0.432 0.053 1.288 17 0.173 0.173 0.132 2.873 18
-0.173
-0.173
-0.132 3.814 1G 0.173 0.173
-0.132 3.814 20
-0.173
-0.173 0.132 2.873 21
-0.173-0.173 0.132 2.873 22 0.173
-0.173
-0.132 3.814 23 0.173
-0.173 0.132 2.873 24
-0.173 0.173
-0.132 3.814 Minimum Safety Factor : 1.288 The anchorage can withstand 1.288 times greater seismic demand j
e Prairie I: land Nuclear Gener ting Plant GIP Rev 2, Co;rected,2/14/92 SCREENING EVALUATION WORK SHEET (SEWS)
Status: Yes Sheet 1 of 11 ID : 145-201 ( Rev. 0 )
l Class : 5. Hortzontal Pumps -
Description : 11 TD AFW PUMP Building : TURB l Floor El. : 695.00 -
l Room, Row / Col: F.5/8.3 Manufactures, Model, Etc. :
SEISMIC CAPACITY VS DEMAND 1.
Elevation where equipment receives seismic input 695.00 2.
Elevaten of seismic input below about 40' from grade (grade = 695.00)
Yes 3.
Equipment has fundamental frequency above about 8 Hz (est. frequency = 33.00)
Yes-4.
Capacity based on:
1.00
- Bounding Spectrum 5.
Demand based on:
1.00
- Design Basis Ground Response Spectrum 1
0.900 G
LIN
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0.000 i i i i t i i!.... -r -i"'i iiniil i i i iii!
i i
i i iiii 0.02 LOG lli 74.30 Capacity... Demand Fde Record Capacity H \\GlP\\ GIP \\ spectra des LabellBounding Spectrum i
Demand 1 H.\\GIPTPROJ0040\\ spectra des MASS POINTSIN/Al BUILDING lGROUNDIDIRECTION] HORIZONTAL lRADI AL DISTIN/AlELEVATIONi695 00 Demand 2 H \\ GIP \\PROJ0040\\ spectra des MASS POINTSIN/AIDUtLDINGIGROUNDIDIRECTION] HORIZONTAL lRADI AL DISTlN/AlELEVATlON1695 00 Does capacity exceed demand?
ym L
h Prairie 1: land Nuclear Generating Plant
. GIP R;v 2, Corrected,2/14/92 SCREENI:4G EVALUATION WORK SHEET (SEWS) -
Status: Yes Sheet 2 of 11 -
ID : 145-201 ( Rev. 0 )
l Class.: 5. Honzontal Pumps Desenption : 11 TD AFW PUMP -
Building : TURB l Floor El. : 695.00 l Room, Row / Col: F.5/8.3 Manufacturer, Model, Etc. :
0AYEATS BOUNDING SPECTRUM
.)
HP/BS Caveat 1 - Earthquake Expenence Equipment Class.
Yes HP/BS Caveat 2 Driver and Pump on Rigid Skid.
Yes HP/BS Caveat 3 - Thrust Bearings in Both Axial Directions.
Yes HP/BS Caveat 4 Check of Long Unsupported Piping.
Yes HP/BS Caveat 6 Base Vibration Isolation System Checked.
Yes HP/BS Caveat 6 Sufficient Stack and Flexibility of Attached Lines.
Yes HP/BS Caveat 7 Adequate Anchorage.
Yes HP/BS Caveat 8 - Potential Chatter of Essential Relays Evaluated.
N/A HP/BS Caveat 9 - No Other Concems.
Yes ls the in:.ont of all the caveats met for Bounding Spectrum?
Y.c3 ANCHORAGE
- 1. The sizes and locations of anchors have been determined.
Yes
- 2. Appropriate equipment charactenstics have been de' ermined (mass, CG, natural freq.,
Yes damping, center nf rotation).
- 3. The type of anchorage is covered by tha GIP.
Yes
- 4. The adequacy of the anchorage installation has been evaluated (weld quality and length, Yes nuts and washers, expansion anchor tightness, etc.)
- 5. Factors affectir g anchorage capacity or margin of safety have been considered: embedment Yes' length, anchor spacing, free-edge distance, concrete strength / condition, and concrete cracking.
- 6. For bolted anchorages, any gaps under the base are less than 1/4.
Yes
- 7. Factors affecting essential relays have been considered: gaps under the base, capacity N/A reduction for expansion anchors.
- 8. The baso has adequate stiffness and the effect of prying action on anchors has been Yes considered.
- 9. The strength of the equipment base and the load path to the CG is adequate.
Yes
- 10. The adequacy of embedded steel, grout pads or large concrete pads have been evaluated.
Yes
- 11. The anchorage capacity exceeds the demand.
Yes Are anchorage requirements met?
Yes 4
?!
m -
m
l Prairie Island Nucle:r Generating Plant GlP R V 2, Corrected, 2/_14/92 -
SCREENING EVALUATION WORK SHEET (SEWS)
Status: Yes Sheet 3 of 11 i
10 : 145 201 ( Rev. 0 )
l Class : 5. Horizontal Pumps Description : 11 TD AFW PUMP Building : TURB l Floor El. : 695.00 l Room. Row / Col : F.5/S.3 Manufacturer, Model, Etc. '
INTERACTION EFFECTS
- 1. Soft targets are free from impact by nearby equipment or structures.
Yes
- 2. If the equipment contains sensitive relays, it is free from all impact by nearby eautpment or N/A structures.
3, Attached lines have adequate flexibility.
Yes
- 4. Overhead equipment or distnbution systems are not likely to collapse.
Yes
- 5. No other adverse concerns were found.
Yes is equipment free of interaction effects?
Yfui IS_ EQUIPMENT SEISMICALLY ADEQUATE?
Yes C.QMMENTS SRT: W. Djordjevic (S&A), M. McKeown (NSP), F. Stille (S&A) and G. Gore (NSP) - 11/21/93.
REF: Dresser ind (Pacific Pumps) Dwgs 46580, Pioneer Dwgs NF-38221-6, NF-38221-4, NF-38221-9 Anchorage:
- The pe;np is anchored onto a concrete pad (3'-6" wide x 14'-4"long x 20" high) by 8 3/4" J-Bolts (4 per side) and the pad is dowelled into the concrete foundation stab. The J-bolts have a short side edge distance of 4-1/8" and long side edge distance of 10" on 3" high grout pad. The pump assembly's weights are: Pump 4150 lbs, Turbine:
1585 lbs, Skid 1650 lbs and Oil Cooler 120 lbs.
- Also, the J-bolt are embedded 8.5" which is less than the minimum allowable embedment of 12" (16D); however the anchor analysis conservatively uses a smaller J-bolt (1/2") thereby meeting the intent of the this caveat.
The piping nozzle loads used in the anchorage analysis were developed in calculation 93C2807-C-016. This analysis is conservative and demonstrates that the anchorage meets the intent of the GIP.
Evaluated by:
Gerry Gore Date:
Walter Djordjevic
Attachment:
Pictures
Attachment:
ANCHOR Report
Pralrls Isl:nd Nuciser Gsnarating Plant GIP Rev 2, Corrected,2/14/92 SCREEMING EVALUATION WORK SHEET (SEWS)
Status: Yes Sheet 4 of 11 ID : 145-201 ( Rev. 0 )
l Class : 5. Honzontal Pumps Desenption : 11 TD,AFW PUMP Building : TURB l Floor El. : 695.00 i Room, Row / Col : F.5/8.3 Manufacturer, Model Etc.
PJCIURES 1
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c Steam Driven Auxiliary Feedwater Pump (145-201) 1 vey Ts*.,ww ggr?
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Prairie tland Nuclear Generating Plant GIP rov 2 Corrected,2/14/92 SCREENING EVALUATION WORK SHEET (SEWS)
Status: Yes Sheet 5 of 11 ID : 145-201 ( Rev. 0 )
l Class : 5. Horizontal Pumps Description : 11 TD AFW PUMP Building : TURB l Floor El. : 695.00 l Room, Row / Col : F.5/8.3 Manufacturer, Model. Etc. -
ANCHOR Report -
Eartheuake_I Response Spectrum : SSE Frequency : GIP - Rigid Percent Damping : GIP 5.00 Spectral Values :
Direction Acce:eration (g's)
North South 0.225 East - West 0.225 Vertical 0.150
" Angle (N S Direction makes with the X Axis): 180.00 Combination Criteria : SRSS Weight 9L; Number of Weights : 4 No Weight X
Y Z
1 4150.00 63.000 19.880 20.000 2
1585.00 120.000 19.875 20.000 3
1650.00 76.500 19.875 2.500 4
120.00 54.000 31.000 8.000 Eatcan.1 Number of External Forces : 4 No Fx Fy Fz X
Y Z
1 1.10E+001 2.82E+002
-0.10E+001 17.000 53.000 18.000 2
1.63E+003 5.58E+002
-3.33E+003 21.000 5.000 18.000 3
1.35E+002
-7.40Ev001 2.22E+002 74.000 18.000 37.000 4
1.20E+002 4.90E+001
-2.94E+002 110.000 18.000 37.000 Momenta; Number of External Moments : 4
~
No Mx
.My Mz 1
-2.40E+001 3.60E+001 7.48E+003 2
-3.80E+004 1.61 E+005 3.33E+004 3
4.68E+003 3.18E+003 1.98E+003
_4 1.63E+003 3.23E+003 1.32E+003 Allowahlen.;
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1 Prairie 1: land Nuclear Generating Plant GIP R2v 2, Corrected,2/14/92
. SCREENING EVALUATION WORK SHEET (SEWS)
Status: Yes Sheet 6 of 11 ID : 145 201 ( Rev. 0 )
l Class : 5. Horizontal Pumps Description : 11 TD AFW PUMP -
Building : TURB l Floor El. : 695.00 l Room, Row / Col: F.5/8.3 Manufacturer, Model. Etc. -
Anchor -
- Number of Anchor types : 1
- Tension
-Shear Ultimate Ultimate inter Inter Saf No.
Dia Manufact Product Tension Shear Coeff Coeff
' Fact 1
1/2 Other J-Bolt (90 6660.00 3330.00 1.00 0.30 1.00 deg)
CQDCIt i Ultimate Stress.: 3000 00 psi.
Reduction Factor : 0.85 Wekt:
Allowable Stress : 30600 psi.
Sudaces; Number of Surfaces : 1 Surface Orientation Direction Direction Direction Comp Comp Comp No Nx Ny Nz 1
0.000 0.000 -
1.000 Anchor Pattern for Surface # 1 w
w w
m a
X Legend for Anchor Patterns
(.
Prairie Island Nuclear Generating Plant GIP RGv 2, Corrected,2/14/92 SCREENING EVALUATION WORK SHEET (SEWS)
Status: Yes Sheet 7 of 11 ID : 145-201 ( Rev. 0 )
l Class : 5. Honzontal Pumps Desenption : 11 TD AFW PUMP Building : TURD l Floor El. : 695.00 l Room, Row / Col: F.5/8.3 Manufacturer, Model, Etc.
Anchor Dotts:
Concreto Lines:
Concrete Points: I R
l:
- O]
L.-
Weld Lines :
Geome.ity_:
Anchou Number of Anchors : 8 Anch X
Y Z
Surf No.
ld Coord Coord Coord Id 1
1 6.000 1.500 0.000 1
2 1
53.000 1.500 0.000 1
3 1
100.000 1.500 0.000 1
4 1
147.000 1.500 0.000 1
5 1
147.000 36.750 0.000 1
6 1
100.000 36.750 0.000 1
7 1
53.000 36.750 0.000 1
0 1
6.000 36.750 0.000 1
CQDcmte Lines :
- of elements per line : 10 Number of Concrete Lines : 4 Start Start Start End End l
End St Line No X Coord Y Coord Z Coord X-Coord Y-Coord Z-Coord Id Width 1
0 000 0.000 0 000 153.000 0.000 0 000 1
3.000 2
153.000 0.000 0 000 153.000 39.750 0.000 1
3.000 3
153 000 39.750 0.000 0.000 39.750 0.000 1
3.000 l 4 0.000 39 750 0 000 0.000 0.000 0.000 1
3.000 Concrete Pointt Number of Concrete Points : 0 Weld Linet
- of elements per line : 4 Number of Weld Lines : 0 D.etennl01 tion _of Reducilonfict0DLI l
l l
Sb 3rairie Island Nuclear Generating Pl:nt GIP R:;v 2, Corrected,2/14/92 -
SCREENING EVALUATION WCRK SHEET (SEWS)
Status: Yes Sheet 8 of 11 ID : 145-201 ( Rev. 0 )
l Class : 5. Honzontal Pumps -
Description : 11 TD AFW PUMP Building : TURB l Floor El. : 695.00 l Room. Row / Col: F.5/8.3 Manufacturer, M@l, Etc. -
Reduction Factor input to Anchor #.1 Adequately Instal ed, Yes Embedment Length : (27.25 in. Min Reqd. to achieve full capacity) i= 8.50 in.
Gap at Threaded Anchor : 0.00 in.
Edge Distance - Edge 1 : 4.13 in.
Crack Size : 0.000 in. - Cracks traverses thru Installation Essentist Relays in Cabinet : No Adequate Equipment Base Strength and Structural Load Path : Yes Embedment Steel and Pads Adequately installed : Yes Reduction Factor input for Anchor # 2
. Adequately Installed : Yes i
Embedment Length : (27.25 in. Min Reqd. to achieve full capacity) := 8,50 in.
Gap at Threaded Anchor : 0.00 in.
Edge Distance - Eage 1 : 4.13 in.
Crack Size : 0.000 in. - Cracks traverses thru installation Essential Relays in Cabinet : No Adequate Equipment Base Strength and Structural Load Pr.th : Yes Embedment Steel and Pads Adequately Installed : Yes Reduction Factor input for Anchor # 3 Adequately Installed : Yes Embedment Length : (27.25 in. Min Reqd. to achievs full capacity) := 8.50 in.
Gap at Threaded Anchor : 0.00 in.
Edge Distance - Edge 1 : 4.13 in.
Crack Size : 0.000 in. - Cracks traverses thru Installation Essential Relays in Cabinet : No Adequate Equipment Base Strength and Structural Load Path : Yes l
Embedment Steel and Pads Adequately Installed : Yes Reduction Factor input for Anchor # 4 Adequately Installed : Yes Embedment Length : (27.25 in. Min Reqd. to achieve full capacity) := 8.50 in.
Gap at Threaded Anchor : 0.00 in.
Edge Distance - Edge 1 ; 4.13 in.
Crack Size : 0.000 in. - Cracks traverses thru installation Essential Relays in Cabinet : No
- Adequate Equipment Base Strength and Structural Load Path : Yes Embedment Steel and Pads Adequately Installed : Yes l
Reduction Factor input for Anchor # 5 Adequately Installed : Yes
'I Embedment length : (27.25 in. Min Reqd. to' achieve full capacity) := 8.50 in.
L 1
Prairie 1:Isnd Nuclear Generating Plant GIP R:V 2, C:rrected,2/14/92 SCREENING EVALUATION WORK SHEET (SEWS)
Status: Yes Sheet 9 of 11 l
ID : 145-201 ( Rev. 0 )
l Class; 5. Horizontal Pumps Desenpten : 11 TD AFW PUMP Building : TURB -
l Floor El. : 695.00 l Room. Row / Col: F.5/8.3 Manufacturer, Model, Etc. -
Gap at Threaded Anchor 0.00 in.
Edge Distance - Edge 1 : 4.13 in.
- Crack Size : 0.000 in.
Cracks traverses thru installation Essential Relays in Cabinet : No Adequate Equipment Base Strength and Structural Load Path : Yes Embedment Steel end Pads Adequately Installed : Yes Reduction Factor input for Anchor # 6 Adequately Installed : Yes Embedment Length : (27.25 in. Min Reqd. to achieve full capacity) := 8.50 in.
Gap at Threaded Anchor : 0.00 in.
Edge Distance - Edge 1 : 4,13 in.
Cf ack Size : 0.000 in.
Cracks traverses thru installation Essential Relays in Cabinet : No Adequate Equipment Base Strength and Structural Load Path : Yes Embedment Steel and Pads Adequately Installed : Yes Reduction Factor input for Anchor # 7 Ariequately installed : Yes Embedment Length : (27.25 in, Min Reqd. to achieve full capac;ty) := 8.50 in.
Gap at Threaded Aachor : 0.00 in.
Edge Distance' Edge 1 : 4.13 in.
Crack Size : 0.000 in. - Cracks traverses thru Installation Essential Relays in Cabinet : No Adequate Equipment Base Strength and Structural Load Path : Yes Embedment Steel and Pads Adequately installed : Yes Reduction Factor input for Anchor # 8 Adequately Installed : Yes Embedment length : (27.25 in. Min Reqd. to achieve full capacity) := 8.50 in.
Gap at Threaded Anchor : 0.00 in.
Edge Distance - Edge 1 : 4.13 in, Crack Size : 0.000 in. - Cracks traverses thru installation Essential Relays in Cabinet : No Adequate Equipment Base Strength and Structural Load Path : Yes Embedment Steel and Pads Adequately Installed : Yes Reduction Factors Data Current : Yes Anc Pall /
Pallr/
No id Valt Vatir RT RN RL RG RS RE RF RC RR RP RB RM 1
1 2026 03 N/A 1 00 1.00 0 40 1 00 1 00 0 82 0 93 1.00 1.00 1 ^0 1.00 1.00 2748 84 N/A 1.00 1 00 1 00 1.00 1.00 0 89 0 93 1.00 1 00 1 00 1.00 1.00 2
1 2026 03 N/A 1.00 1.00 0 40 1.00 1 00 0 82 0 93 1.00 1 00 1.00 1.00 1.00 2r48 84 N/A 1.00 1.00 1.00 1 00 1.00 0.89 0 93 1.00 1.00 1.00 1.00 1.00 3
1 2026 03 N/A 1.00 1.00 0 40 1.00 1.00 0 82 0 93 1.00 1.00 1.00 1 00 1.00
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Prairie Island Nuclear Generating Plant GIP RCv 2, Corrected,2/14/92
-(
SCREENING EVALUATION WORK SHEET (SEWS)
Status: Yes Sheet 10 of 11 ID : 145 201 ( Rev. 0 )
l Itass : 5. Horizontal Pumps Desenption : 11 TD AFW PUMP -
Building : TURB l Floor El. : 695.00 l Room. Row / Col : F.5/8.3 j
Manufacturer, Model, Etc.
2748 84 N/A 1.00 1.00 1.00 1.00 1 00 0 89 0 93 1 00 1 00 1.00 1.00 1.00 4
1 2026 03 N/A 1.00 1.00 0 40 1.00 1.00 0 82 0 93 1.00 1.00 1.00 1.00 1.00 2748 84 N/A 1.00 1.00 1.00 1.00 1.00 0 89 0 93 1.00 1 00 1 00 1.00 1.00 5
1 2026 03 N/A 1.00 1.00 0 40 1.00 1.00 0 82 0 93 1.00 -
1 00 1.00 1.00 1 00 2748 84 N/A 1 00 1 00 1.00 1 00 1.00 0 89 0 93 1.00 1.00 1.00 1.00 1.00 l
6 1
2026 03 N/A 1.00 1.00 0 40 1.00 1 00 0 82 0 93 1.00 1.00 1.00 1.00 1.00 2748 84 N/A 1.00 1.00 1.00 1.00 1.00 0 89 0 93 1.00 1.00 1.00 1.00 1.00 1
7 1
2026.03 N/A 1.00 1.00 0 40 1.00 1.00 0 82 0 93 1.00 1.00 1.00 1.00 1.00 2748 84 N/A 1.00 1.00 1.00 1.00 1 00 0 89 0 93 1.00 1.00 1.00 1 00 1.00 8
1 2026 03 N/A 1.00 1.00 0 40 1 00 1.00 0.82 0 93 1.00 1.00 1.00. 1.00 1.00 2748 84 N/A 1.00 1.00 1.00 1 00 1.00 0 89 9 93 1.00 1.00 l 1.0011.00 1.00 Jgend_:
N/A-
= Not Applicable Pall
= Allowable Pull without Reduced inspection Vall
= Allowable Shear without Reduced inspection Palir
= Allowable Pull with Reduced Inspection Vallr
= Allowable Shear with Reduced inspection
= Outlier
'X
= Reduction Factor Not Used RT
= Reduction Factor 'or Type of Anchorage -
r RN
= Reduction Factor for Installation Adequacy RL_
u Reduction Factor for Embedment RG
= Reduction Factor for Gap at Anchors RS
= Reduction Factor for Spacing RE
= Reduction Factor for Edge Distance RF
= Reduction Factor for Concrete Strength RC
= Reduction Factor for Concrete Cracks RR
= Reduct:on Factor for Essential Relays RP
= Reduction Factor for Base Stiffness and Prying Action RB
= Reduct!cn Factor for Base Strength and Load Path RM
= Reduction Factor for Embed. Steel and Pads Analysis Res.ultsL1 Analysis Performed : Yes
' Type of Analysis : Regular Spectral Accelerations (G's)
No N-S E-W l
Vertical Safety Factor 1
0.225 0.090
O.060 12.065 2
-0.225
--0.090
-0.060 10.065
~
3
-0.225 0.090 0.060 10.358 4
0.225
-0.090
-0.060 11.986 5
0.225 -
-0.090 0.060 11.948
-6
-0.225 0 090
-0.060 10.358 0.225 0.090
-0.060 12.279 8
-0.225
-0.090 d
0.060 10.065
Prairie 1: land Nuclear Generating Plant -
GIP R;v 2, Corrected,2/14/92 -
SCREENING EVALUATION WORK SHEET (SEWS)
Status: Yes e-Sheet 11 of 11 10 : 145 201 ( Rev. 0 )-
l Class : 5 Horizontal Pumps -
Desenpton : 11 TD AFW PUMP,
Building : TURB l Floor El. : 695.00 -
l Room, Row / Col: F.5/8.3 Manufacturer, Model, Etc. -
9 0.090 0.225 0.060 10.084
~iOT
-0.090
-0.225
-0.0A0 10.420
~
11 0.090
-0.225 0.060 9.739 12
-0.090 0.2'5
-0.060 11.12F ' I 13
-0.090-0.225 0.060 9.644 14 0.090
-0.225 0.060 11.210 15 0.090 0.225 0.060
' 7 1.924 16
-0.090
-0225 0.060 9.191 17 0.090 -
0.090 tf150 15.632 18
-0.090
-0.090 0.t50 20.740 19 0090 0.090
-0.150 24.571 20~
-0.090
-0.090 0.150 14.415 21
-0.090 0.090 0.150 14.385
-22 0.090
-0.090
-0.150 23.112 23 0.090
-0.090 0.150 15.617
~
24
-0.090 0.090
-0.150 21.344 Minimum Safety Factor ; 9.191' The sqchorage can withstand 9.191 times greater seismic demand l
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ATTACHMENT 5-CALCULATIONS / SEWS 053-381 55300 PNL 132 PNL 113 SV-37460 SV-37022 181-2R1-145-041 145-201 B-1 135-021 1
153-021 253-021-053-251 153-011 LAR 005 i
LAR 010 i
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a Nonhem $tatee Power Company. Prestie island Nuclear Generating Plant GIP Rev 2, Corrected,2/14/92 SCREENING EVALUATION WORK SHEET (SEWS).
Status: Yes Sheet 1 of 3 10 : 053 381 (Rev. 0) l Class : 21 - Tanks and Heat Exchangers Desenpton : 121 CONTROL ROOM CHILLED WATER EXPANSION TANK Building ; AUX l Floor El. : 755.00 l Room. Row / Col:
Manufacturer, Model, Etc. :
BASIS : Extemal analysis
- 1. The buckhng capacity of the shell of a large, flat-bottom, vertical tank is equal to cr greater N/A than the demand.
2, The capacity of the anchor bolts and their embedments is equal to or greater than the.
Yes demand.
- 3. The capacity of connectons betweenlhe anchor bolts and the tank shell is oqual to or Yes greater than the demand.
- 4. Attached piping has adequate flexibility to accommodate the moton of a large, flat-bottom, N/A vertical tank.
,5. A nng type foundation is not used to support a large, flat-bottom, vertical tank.
N/A lS EQUjeMENI.AEISMICALLY ADEQUAIE7 Yan GQMMENIA SRT: F. Stille (S&A) and G. Gore (NSP)- 10/11/95 Vertically mounted ASME tank with elliptical heads and mounting skirt. Skirt bolted to floor with steel angles and 1/2" shell anchors. See d6cument for configuration and anchorrge evaluation.
Interaction: No potentialinteractions were observed.
Evaluated by:
Date:
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Attachment:
Pictures
Attachment:
Anchorage Anelysis of 053-381 and 053-382 g
Northern States Power Comp:ny Prairts 1:1:nd Nucl: r Generating PI:nt GIP Rev 2, Corrccted,2/14/92 SCREENING EVALUATION WORK SHEET (SEWS)
Status: Yes Sheet 2 of 3 ID : 053-381 (Rev. 0) l Class : 21 Tanks and Heat Exchangers Desenption : 121 CONTROL ROOM CHILLED WATER EXPANSION TANK Building : AUX l Floor El. : 755.00 l Roorn, Row / Col:
Manufacturer, Model. Etc..
PlcTURES
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Northern States Power Company Prairk Islated Nuclear Generating Plant GIP Rev 2, Corrected,2/14/92 SCREENING EVALUATION WORK SHEET (SEWS)
Status: Yes Sheet 3 of 3-ID : 053 381 (Rev. 0) l Class : 21 Tanks and Heat Exchangers Desenption : 121 CONTROL ROOM CHILLED WATER EXPANSION TANK Building : AUX l Floor El. : 755.00 l Room. Row / Col:
Manufacturer, Model. Etc. -
Anchormae Analysis of oss sai and 053-382 I
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Northern States Power Company. Prairle island Nuclear Generating Plant GIP Rev 2, Corrected,2/14/92 9,*
SCREENING EVALUATION WORK SHEET (SEWS)
Status: Yes Sheet 1 of 5 ID : 55300 ( Rev. 0 )
l Class : 20. Instrumentation and Control Panels and Cabinets Desenption : 01 DSL GEN ENG/ GEN PANEL (EGP)
Building : TURB l Floor El. : 695.00 l Room, Row / Col: KA.4/2.8 Manufacturer, Model, Etc..
SEISMIC CAPACITY VS DEMAND 1.
Elevation where equipment receives seismic input 695.00 2.
Elevation of seismic input below about 40' from grade (grade = 695.00)
Yes 3.
Equipment has fundamental frequency above abc,ut 8 Hz (est. frequency = 8.00)
Yes 4.
Capacity based on:
1.00
- Bounding Spectrum 5.
Demand based on:
1.00
- Design Basis Ground Response Spectrum 2.000
/
G LOG
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e i i ii 0.100 1.00 LOG Hz 100.00 Capacity..... Demand File Record Capacity H%lPiGIP\\ spectra des LabellBourviing Spectrum Demand 1 HMIPPROJ0040\\ spectra. des MASS POINTSIN/AlBUILDINGIGROUNDjDIRECTIONIHORIZONTALlRADI i
AL DIST]N/AIELEVATIONl695.00 Demand 2 H41P\\PROJ0040\\ spectra.oes MASS POINTS lN/AjBUILDINGlGROUNDlDIRECTIONjHORIZONTALlRADI AL DISTlN/AIELEVATIONi695 00 Does capacity exceed demand?
Y.e.s
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'i Northern States Power Company Prairie Island Nuclear Generating Plant GlP R: *, Corrected,2/14/92
[**
SCREENING EVALUATION WORK SHEET (SEWS)
Status ses Sheet 2 of 5 ID : 55300 ( Rev. 0 )
l Class : 20. Instrumentaten and Control Panels and Cabinets Descnotion : D1 DSL GEN ENG/ GEN PANEL (EGP)
Building : TURB l Floor El. : 695.00 l Room, Row / Col: KA.4/2.8 Manufacturer, Model Etc. -
CAVEATS BOUNDING SPECTRUM Yes l&C/BS Caveat 1 - Earthguake Expenence Equipment Class.
l&C/BS Caveat 2 - Computers and Programmable Contro:lers Evaluated Separately.
N/A I&C/BS Caveat 3 - Stnp Chart Recorders Evaluated.
N/A I&C/BS Caveat 4 - Structural Adequate.
Yes l&C/BS Caveat 5 - Adjacent Cabinets or Panels Bolted Together.
Yes l&C/BS Caveat 6 - Drawers or Equipment on Slides Restrained.
Yes I&C/BS Caveat 7 - Doors Secured.
Yes l&C/BS Caveat 8 - Sufficient Slack and Flexibility of Attached Lines.
Yes l&C/BS Caveat 9-Adequate Anchorage.
Yes I&C/BS Caveat 10 - Potential Chatter of Essential Relays Evaluated.
Yes l&C/BS Caveat 11 - No Other Concems.
Yes is the intent of all the caveats met for Bounding Spectrum?
Ycs ANCWORAGE
- 1. The sizes and locations of anchors have been determined.
Yes
- 2. Appropnate equipment charactenstics have been determined (mass, CG, natural freq.,
Yes damping, center of rotation).
- 3. The type of anchorage 19 covered by the GIP.
Yes
- 4. The adequacy of the anchorage installation has been evaluated (weld quality and length, Yes nuts and washers, expansion anchor tightness, etc.)
- 5. Factors affectng anchorage capacity or margin of safety have been considered: embedment Yes length, anchor spacing, free-edge distance, concrete strength / condition, and concrete cracking.
- 6. For bolted anchorages, any gaps under the base are less than 1/4.
Yes*
- 7. Factors affecting essential relays have been considered: gaps under t*e base, capacity Yes reduction for expansion anchors.
- 8. The base has adequate stiffness and the effect of prying acton on anchors has been Yes considered.
~. The strength of the equipment base and the load path to the CG is adegaate.
Yes 9
- 10. The adequacy of embedded steel, grout pads or large concrete pads have been evaluated.
Yes 11 The anchorage capacity exceeds the demand.
Yes Are anchorage requirements met?
Y.es l
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i Northern States Power Company. Prairie islant! Nuclear Generating Plant GIP Rev 2, Corrected,2/14/92 m
SCREENING EVALUATION WORK SHEET (SEWS) _
Status: Yes Sheet 3 of 5 10 : 55300 ( Rev. 0 )
l Class 20. Instrumentaten and Control Panels and Cabinets Desenpton : D1 DSL GEN ENG/ GEN PANEL (EGP)
Buildutg : TURB l Floor El. : 695.00 l Room, Rcw/ Col : KA.4/2.8 Manufacturer, Model. Etc. ?
INTERACTION EFFECTS "1. Soft targets are free from impact bv nearby equipment or structures.
Yes
- 2. If the equipment contains sensitive relays, it is free from alt impact by nearby equipment or Yes structures.
- 3. Attached lines have adequate flexibility.
Yes
- 4. Overhead equipment or distnbution systems are not tkely to collapse.
Yes
- 5. No other adverse concems were found.
Yes is equipment free of interaction effects?
Yta IS EQUIPMENT SEISMICALLY AD_ EQUATE?
Yes COMMENTS SRT: W Djordjevic (S&A) and G. Gore (NSP)-11/1/95.
REF: NF-3829810 Rev. AH, NF-38312 5 Rev. C and NF-383131 Rev. HH Anchorage:
The pLnel,106" x 30" x 9h high, is anchored to a 2' deep concrete pad by 12 - 1/2" J-Bolts (AB-51). Also, the cabinet base is shimed 1.25" with no grout pad. Since the base is property shimed, the intent of the 0.25" gap is met, but the anchors will be subjected to some bending, hence, it is conservative to use the methodogy set forth in EPRI TR 103960 (" Recommend Approaches for Resolving Anchoraga Outliers") to analyze the anchorage.
The attached anchorage evaluation use the methodology of EPRI TR-103960 to show that the cabinets are adequately anchored.
Evaluated by:
Date:
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Attachment:
Pictures
Attachment:
Anchorage Evaluation i
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4, North:rn States Powsr Company. Prairls 121:nd Nucle:r G:nerating PI:nt GlP Rev 2 Corrected,2/14/92 I
SCREENING EW LUATION WORK SHEET (SEWS)
Status: Yes Sheet 4 of G 10 : 55300 ( Rev. 0 )
l Class : 20. Instrumentation and Control Panels and Cabinets Oesenption : D1 DSL GEN ENG/ GEN PANEL'. (EGP)
Building : TURB l Floor El. : 695.00 l Room, Row / Col: KA.4/2.8 j
Manufacturer, Model. Etc.
PICTURES r.
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4 Northern States Power Company. Prm6th lonand Nuclear Generating Plant GIP Rev 2 Corrected,2/14/92
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SCREENING EVALUATION WORK SHEET (52WS)
Status: Yes Sheet 5 of 6 ID : 65300 ( Rev. 0 )
l Class : 20. Instrumentation and Control Panels and Cabinets Desenption : D1 DSL GEN ENG/ GEN PANEL (EGP)
Building : YURS l Floor El. : 695.00 l Room. Row / Col : KA 4/2.8 Manufacturer, Model, Etc. -
Anchorage Evaluation r
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.e Northem Statee Power Company. Pro 6fte le6end Nuclear Generating Piem GlP Rev 2. Cor octed. 2/14/92 SCREENING EVALUATION WORK SHEET (SEWS)
Status: Yes Sheet 1 of 4 ID : PNL 132 ( Rev. 0 )
l Class : 14. Distnbution Panels Desenpton : AC DISTRIBUTION PANEL 132 Building : TURB Floor El. : 695.00 Room, Row / Col: E.8/9.1 NEAR 123 AIR COMPR Manufacturer, Model. Etc. :
SEISMIC CAPACliY V8 DEMAND 1.
Eky'aton where equipment receives seismic input 695.00 2.
Elevation 74 seismic input below about 40' from grade (grade = 695.00)
Yes 3.
Equipment i.is fundamental frequency above about 8 Hz (est. trequency a 11.00)
Yes 4.
Capacity base on:
1.00
- Bounding Spectrum 5.
Demand based 2n:
1.00
- Design Basis Ground Response Spectrum 2.000
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0.100 i
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i i i e i LOO LOG Hz 100.00 Capacity..... Demand Fa Record Capacity _
H GIPGIP$mpectra oes Label lBoundin0 Spectrum Demand 1 H GIPpROJ0040\\ spectra oes MASS POINTSIN/AIBUILDINGl GROUND lDIRECTIONjHORIZONTALlRADI AL DISTlN/AJELEVATION1695 00 Demand 2 H \\04P4)ROJ0040\\ spectra.oes MASS POINTSIN/AlBUILDINulGROUNDIDIRECTIONIHORt20NTAllRADI AL CISTINIA! ELEVATION!695 00 Does capacity exceed demand?
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Northem States Power Company Pro 6tte loland Nuclear Generating Plant GIP Rev 2, Corrected,2/14/92 SCREENING EVALUATION WORK SHEET (SEWS)
Status: Yes Sheet 2 of 4 ID : PNL 232 ( Rev 0 )
l Class : 14. Distnbution Panels Desenption : AC DISTRIBUTION PANEL 132 Building : TURB Floor El. : 695.00 Room, Row / Col: E.8/9.1 NEAR 123 I
AIR COMPR Manufacturer, Model, Etc. :
CAVEATS. BOUNDING SPECTRUM DP/BS Caveat 1. Earthquake Exponence Equipment Class.
Yes DP/BS Cavest 2. Contains only Circuit Breakers and Switches.
Yes DP/BS Caveat 3. Doors Secured.
Yes DP/BS Caveat 4 Adjacent Cabinets Botted Together, N/A DP/BS Caveat 5. General Configuration,Similar to NEMA Standards.
Yes Yes DP/BS Caveat 6 Adequate Anchorage.
DP/BS Caveat 7. Potential Chatter of Essential Ae;Fg Evaluated.
N/A DP/BS Gavest 8 No Other Concems.
Yes la the intent of all the caveats met for Bounding Spectrum?
YAt 1
ANCHORAGE
- 1. The sizes and locations of anchors have been determined.
Yes
- 2. Appropnate equipment charactenstics have been determined (mass, CG, natural freq.,
Yes damping, center of rotstion).
- 3. The type of anchorage is covered by the GIP.
Yes
- 4. The adequ'.acy of the anchorage installation has been evaluated (weld quality and length, Yes nuts and washers, expansion anchor tightness, etc.)
- 5. Factors affecting anchorage capacity or margin of safety have been considened: embedment Yes length, anchor spacing, free-edge distance, concrete strength / condition, and concrete cracking.-
- 6. For bolted anchorages, any gaps under the base are less than 1/4.
Yes
- 7. Factors affecting essential relays have been considered; gaps under the base, capacity N/A reduction for expansion anchors.
- 8. The base has adequate stiffness and 'he effect of prying action on anchors has been Yes t
considered.
- 9. T he strength of the equipment base and the load prsth to the CG is adequate.
Yes
- 10. The adequacy of embedded steel, grout pods or large concrete pads have been evaluated.
N/A
- 11. The anchorage espacity exceeds the demand.
Yes Are anchorage requirements met?
Yes
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Northem States Power Company. Pro 6fte Wand Nuoleer Genre 6ng Plant C4P Rev 2. Corrected,2/14/92 SCREENING EVALUATION WORK SHEET (SEWS)
Status: Yes i
Sheet 3 of 4
+
ID : PNL 132 ( Rev. 0 )
l Class : 14. Detributen Panels 4
Descnptnon : AC DISTRIBUTION PANEL 132 Building : TURB Floor El. : 695.00 Room, Row / Col: E.8/9.1 NEAR 123
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AIR COMPR
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Manufacturer, Model. Etc. :
i INTERACTION EFFECTS
- 1. Soft targets are free from impact by nearby equipment or structures.
Yes
- 2. If the equipment contains sensitive relays, it is free from all impact by nearby equipment or N/A 1
- structures.
- 3. Attached lines have adequate flexibility.
Yes
- 4. Overhead equipment or distnbuttor, systems are not likely to collapse.
Yes
]
- 5. No other adverse concems were found.
Yes la equipment free of interaction effects?
Yan 181QulPMENT SElSMICALLY ADEQUATE 7 Yan C.QMMENTS SR1. W. Djordjevic (S&A) and G. Gore (NSP).11/1/95.
This is a wall mounted panel of dimension 26"Wx45"Hx6.5"D and anchored on a R/C wall by 8 - 3/8" CEAs. The panel was tug tented and judged to be OK. Photo: F1 16 i
Evaluated by:
Date:
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Attachment:
Pictures t
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North:m $ tat s Power Comp:ny. Prairis tal:nd Nuct: r G:n:r: ting Plant GIP Rev 2, Corrected,2/14/92 j
SCREENING EVALUATION WORK SHEET (SEWS)
Status: Yes l
Sheet 4 of 4 i
ID : PNL 122 ( Rev. 0 )
l Class : 14. Distnbution Panels l
l Desenption : AC DISTRIBUTION PANEL 132 l
Building : TURB Floor El. : 695.00 Room. Row / Col : E.8/9.1 NEAR 123 l
l AIR COMPR l
j Manufacturer. Model. Etc.
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Northom States Power Company. Pro 6tte loland Nuclear Generseng Plant GIP Rev 2 Corrected,2/14/92 SCREENING EVALUATION WORK SHEET (SEWS)
Status: Yes Sheet 1 of 4 i
10 : PNL 113 ( Rev. 0 )
l Class : 14. Dtstnbution Panels Desenpton : INSTR BUS 111 PANEL (BLUE) 113 Building : TUR8 l Floor El : 715 00 l Room. Row / Col: G.1/8.0 Manufacturer Model. Etc. :
I SElSMIC CAPACITY VS DEMAND 1.
Elevaton where equipment receives seismic input 715.00 2.
Elevaten of seismc input below about 40' from grade (grade = 695.00)
Yes 3.
Equipment has fundamental frequency above about 8 Hz (est. frequency = 11.00)
Yes 4.
Capacity baM on:
1.00
- Bounding Spectrum 5.
Demand based on:
1.00
- Des 6gn Basts Ground Response Spectrum 2.000 7
i 2
/
G LOG
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0.100 i
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i i i ii 1.00 LOG l!z 100.00 Capacity..... Demand i sie Record Oapseny H GlPCIP\\ spectre des Label! Bounding Spectrum Demand 1 H.GIPPROJ0040\\ spectra des MASS POINTSIN/AlBUILDINGl GROUND l DIRECTION l HORIZONTAL lRADI i
AL 01STlN/AlELEVATlON!695 00 Demand 2 H gip \\PROJ0040\\ spectre des MASS POINTS lN/AjBUILDINGl GROUND lDIRECTIONjHORIZONTAllRADI AL DISTIN!AlELEVATIONf695 00 Does capacity exceed demand?
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Northern states Power company. Prome miend Nuc6 ear Genereung Plant GlP Rev 2 Corrected,2/14/92 SCREENING EVALUATION WORK SHEET (SEWS)
Status: Yes
+
Sheet 2 of 4 10 : PNL 113 ( Rev. 0 )
l Class : 14. D stnbuten Panels
[
Desenption : INSTR BUS Ill PANEL (BLUE) 113 i
Building : TURB l Floor El. : 715.00 l Room, Row / Col: G.1/8.0
[
Manufacturer, Model, Etc.
CAVEATS. BOUNDING SPECTRUM DP/BS Caveat I. Earthquake Exponence Equipment C'sss.
Yes DP/BS Caveat 2. Contains only Circuit Breakers and Switches.
Yes
_P/BS Caveat 3. Doors Secured.
Yes D
DP/BS Caveat 4 Adjacent Cabinets Bolted logether.
N/A f
DP/BS Caveat 5. Genwal Configuration Similar to NEMA Standards.
Yes DP/BS Caveat 6 Adequate Anchorage.
Yes DP/BS Cavest 7. Tontial Chatter of Essential Relays Evaluated.
N/A DP/BS Caveat 8. No Other Concerns.
Yes I
la the intent of all the caveats met for Bounding Spectrum?
Yan ANCHORAGE
- 1. The sizes and locations of anchors have been determined.
Yes
- 2. Appropnate equipment charactenstics have been determined (mass, CG, natural freq.,
Yes damping, center of rotation).
- 3. The type of anchorage is covered by the GIP.
Yes
- 4. The adequacy of the anchorage installation has been evaluated (weld quality and length, Yes nuts and washers, expansion anchor tightness, etc.)
- 5. Factors affecting anchtfrage capacity or margin of safety have been considered: embedment Yes length, anchor spacing, free edge distance, concrete strength / condition, and concrete cracking.
- 6. For bolted anchorages, any gaps under the base are less than 1/4.
Yes
- 7. Factem affecting essential relays have been considered; gaps under the base, capacity N/A reduction for expansion anchors.
S. The base has adequate stiffness and the effect of prying action on anchors has been Yes considered.
j
- 9. The strength of the equipment base and the load path to the CG is adequate.
Yes
- 10. The adequacy of omt:edded steel, grout pads or large concrete pads have been evaluated.
N/A
- 11. The anchorage capacity exceeds the demand.
Yes Are anchorage requirements met?
Xfts INTERACTION EFFECTS
- 1. Soft targets are free from impact by nearby equipment or structures.
Yes
- 2. If the equipment contains sensitive relays, it is free from all impact by nearby equipment or N/A Structures.
- 3. Attached lines have adequate flexibility.
Yes
- 4. Overhead equipment or distnbution systems are not likely to collapse.
Yes
- 5. No other adverse concems were found.
Yes Is equipment free of interaction effects?
Yfts
I
- 6 Northem States Power Company. Pro 6 rte bland Nuc6eer Generseng Plant GIP Rev 2, Corrected,2/14/92 SCREENING EVALUATION WORK SHEET (SEWS)
Status: Yes Sheet 3 of 4 ID : PNL 113 ( Rev. 0 )
l Class : 14. Distnbution Panels Desenpton : INSTR BUS Ill PANEL (BLUE) 113 Building : TURB l Floor El. : 715.00 l Room. Row / Col: G.1/8.0 l
Manufacturer, Model. Etc. -
i 1
I 181QUlPMENI_SE18AllCALL1ADEQUAIE1 Yan GQAlt4ENTS SRT: W. Djordjevic (S&A) and G. Ridder (WPS). 5/23/94.
Anchorage:
Panel is wall mounted. The panel dimensions are: 20Wx36Hx6D. Anchored by 4 1/2" CEA into R/C wall. Tug tested and judged to be OK.
No seismic interactions.
Evaluated by:
Date:
NDZ wyes-
^
Attachment:
Pictures
l- _ _ _.
l Northem States Power Comp:ny. Prairb ist:nd Nuclxr Generating Pl:nt GIP Rev 2, Corrected,2/14/92 l
SCREENING EVALUATION WORK SHEET (SEWS)
Status: Yes Sheet 4 of 4 i
10 : PNL 113 ( Rev. 0 )
l Class : 14. Distnbution Panels Desenption : INSTR BUS til PANEL (BLUE) 113 j
Building : TtlRB l Floor El. : 715.00 l Room. Row / Col : G.1/8.0 l
Manufacturer, Model. Etc.
P_lGI.URES 1
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t' Northom Ssstee Pourw Company. Pts 6ne loland Nuclear Genersong Plant GtP Rev 2, Corrected,2/14/92 I
SCREENING EVALUATION WORK SHEET (SEWS)
Status: Yes 4
Sheet 1 of 4 ID : SV.37460 ( Rev. 0 )
i Class : 8. Motef-Operated and Soleno6d Operated Valves
~
Oesenpton : UNIT 1 TRAIN A CHILL WTR/CLG M/fflSOL SV I
i Building : CNTMT l Floor El. : 749.00 l Room, Row / Col: 13/330 Manufacturer. Model. Etc. :
SEISMIC CAPACITY VS DEMAND 1.
Elevaton where equipment receives seisme input 733J5 2.
Elevation of seisme input below about 40' trom grade (grade = 695.00)
Yes 3.
Equipment has fundamental frequency above about 8 Mz (est. frequency = )
N/A 4.
Capacity based on:
1.00
- Bounding Spectrum 5.
Demand based on:
1.00
- Design Basis Ground Responst Spectrum 2.000 7
2
/
0 LOG
.. '................ ~ ~.....,,,, ' ' "
+
iil 0.100 i
i i
i i i t
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i i ie i 1,00 LOG Hz 100.00 Capacity..... Demand File Record Capac#ty H GIPGIPimpectre des Label) Bounding Spectrum Demand 1 H.GIPPROJ0040\\ spectra des MASS POINTS lN/Al BUILDING l GROUND lDIRECTIONjHORIZONTALlRADI AL DISTlN/Al ELEVATION!695 00 Demand 2 H.GlPPROJ0040\\ spectra des MASS POINTS lN/Al BUILDING l GROUND l DIRECTION l HORIZONTAL lRADI AL DISTIN/AIELEVATIONI695 00 Does capacity exceed demand?
Yes j
r l *. 4 Northom States Power Company. Pro 6tte lelend Nuoleer Generseng Plant GIP Rev 2 Corrected 2/14/92 i
1 SCREENING EVALUATION WORK SHEET (SEWS)
Status: Yes Shoot 2 of 4 10 : SV.37460 ( Rev. 0 )
l Class : 8. Motor-Operated and Solenoid-Operated Valves i
Desenption : UNIT 1 TRAIN A CHILL WTR/CLG WTR ISOL SV i
Building : CNTMT l Floor El. : 749.00 l Room, Row / Col: 13/330 Manufacturer. Model. Etc. '
CAVEATS. BOUNDING SPECTRUM
\\
MOV/BS Caveat 1. Earthquake Exponence Equipment Class.
Yes MOV/BS Caveat 2. Valve Body Not of C&st iron.
Yes MOV/BS Caveat 3. Valve Yoke Not of Cast Iron.
N/A l
MOV/BS Caveat 4. Mounted on 1 inch Diameter Pipe Line or Greater.
N/A MOV/BS Cavest 5. Valve Operator Cantilever Length for Motor-Operated Valves.
N/A MOV/BS Caveat 6 Actuator and Yoke Not Independently Braced.
Yes MOV/BS Caveat 7. Sufficient Slack and Flexibility of Attached Lines.
Yes MOV/BS Caveat 8. No Other Concems.
Yes
[
la the intent of all the caveats met for Bounding Spectrum?
- Yan i
INTERACTION EFFECTS i
I Yes
- 1. Soft targets are free from impact by nearby equipment or structures.
- 2. If the equipment contains sensittve rolays, it is free from all impact by nearby equipment or N/A structures.
- 3. Attached lines have adequate flexibility.
Yes
- 4. Overhead equipment or distnbution systems are not likely to collapse.
Yes
- 5. No other adverse concerns were found.
Yes i
is equipment free of interaction effects?
Yet 13 EQUIPMENT SEISMICALLY ADEQUATE?
Yes COMMENTS 4
SRT: M. McKeown (NSP) and G. Gore (NSP).10/23/95.
Capacity:
BSCav.2: Data was not available for this valve, but its body is not suspected to be cast iron.
BSCav.4&5: This small solenoid valve is rigidly attached to a well supported steel structure which is made of
- plates, angles and channels weilded together. The soleniod was tug tested and judged seismically rugged by -
SRT.
Interaction:
No potential interactions were observed.
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Northom States Power Cmpany. Pro 6r6e totend Nuclear Generseng Plant GIP Rev 2 Corrected,2/14/92 I
SCREENING EVALUATION WORK SHEET (SEWS)
Status: Yes Sheet 3 of 4
~~
ID : SV 37460 ( Rev. 0 )
l Class : 8. Motor Operated and Solenoid Operated Valves Desenpton : UNIT 1 TRA'N A CHILL WTR/CLG WTR ISOL SV Building : CNTM1 l Floor El. : 749.00 l Room. Row / Col: 13/330 Manufacturer, Model. Etc. -
Evaluated by:
Date:
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Attachment:
Pictures 4
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t Norttern Stat:0 Power Cornp:ny. Pr-tris I:l:nd Nuct:cr Genercting Pl:nt GIP Rev 2, Correct 0d,2/14/92 SCREENING EVALUATION WORK SHEET (SEWS)
Status: Yes l
i e
I Sheet 4 of 4 l
ID : SV 37,460 ( Rev. 0 )
l Class : 8. Motor-Operated and Solenoid-Operated Valves
~
j Desenptu : UNIT 1 TRAIN A CHILL WTR/CLG WTR ISOL SV i
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Building : CNTM1 l Floor El. : 749 00 l Room Row / Col: 13/330 J
Manufacturer, Model. Etc.
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I Prairie Island Nuclear Generating Plant GlP R;v 2, Corrected,2/14/92 l
SCREENING EVALUATION WORK SHEET (SEWS)
Status: Yes Sheet 1 of 4 ID : SV-37022 ( Rev. 0 )
l Class : 8. Motor Operated and Soler.osd-Operated Valves Desenption : 121 CONT RM HNDLR OA SPLY STM EXCL B SV Building : AUX Floor El. : 761.00 Room, Row / Col: ON W SIDE WALL G.5/7.3 Manufacturer, Model. Etc.
SEISMIC C# PACITY VS DEMAND 1.
Elevation where equipment recetves seismic input 755.00 2.
Elevation of seismic input below about 40' from grade (grade = 695.00)
N/A 3.
Equipment has fundamental frequency above about 8 Hz (est. frequency = 0.00)
N/A 4.
Capacity based on:
1.50
- Bounding Spectrum 5.
Demand based on.-
1.00
- Conservative Design Floor Response Spectra 2.000 l\\
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e i iiisi 0.20 LOG Hz 100.00 Capacity.... Demand Fste Record Capacity H \\GIPGIP\\ spectra des LabellBounding Spectrum Demand 1 H \\GlPJ'HOJ0040\\ spectra des DulLDINGl Auxiliary ConcretelELEVATIONI755 001DIRECTIONjHOR120NTAllMASS POINTSl291 RADIAL DISTl100 Demand 2 H OtPiPROJ0040\\ spectra des DulLDING} Auxiliary Concrete l ELEVATION 1755 00lDIRECTIONjHORIZONTAllMASS POINTS l291 RADIAL DIST1100 Does capacity exceed demand 7 1e.3 i
L
Prair6e Island Nuclear Generating Plant -
GIP R;v 2, Corrected,2/14/92 e
SCREENING EVALUATION WORK SHEET (SEWS)
Status: Yes Sheet 2 of 4 ID : SV 37022_/_Rev 0 )
l Class : 8. Motor-Operated and Solenoid-Operated Valves Description : 11.1 CONT RM HNDLR OA SPLY STM EXCL B SV Building : AUX Floor El. : 761.00 Room, Row / Col: ON W SIDE WALL G.5/7.3 l
Manufacturer, Model, Etc. -
CAVEATS. BOUNDING SPECTRUM l
t MOV/BS Caveat 1. Earthquake Expenence Equipment Class.
Yes MOV/BS Caveat 2 Valve Body Not of Cast iron.
Yes MOV/BS Caveat 3. Valve Yoke Not of Cast iron.
N/A MOV/BS Caveat 4 Mounted on 1. Inch Diameter Pipe Line or Greater.
N/A MOV/BS Caveat 5. Valve Operator Cantilever Length for Motor Operated Valves.
N/A MOV/BS Caveat 6. Actuator and Yoke Not independently Braced.
Yes MOV/BS Caveat 7. Sufficient Slack and Flexibility of Attached Lines.
Yes MOV/BS Caveat 8 No Other Concerns.
Yes is the intent of all the caveats met for BoundMg Spectrum?
Y.t1 INTERACTION EFFECTS
- 1. Soft targets are free from impact by nearby equipment er structures.
Yes 2, if the equipment contains sensitive relays, it is free from all impact by nearby equipment or N/A l'
structures.
- 3. Attached lines have adequate floxibility.
Yes
- 4. Overhead equipment or distnbution systems are not likely to collapse.
Yes
- 5. No other adverse concerns were found, Yes Is equipment free of interaction effects?
Yes 18 EQUIElENI_SElSMICALLY_ADhQUAIE2 Yes COMMENIS SRT: W Djordjevic (S&A), M. McKeown (NSP) and G. Ridder (WPS). 5/26/94 Capacliy vs. Demand The seismic demand exceeds the capacity at a low frequency, but it is acceptable because the SV unit is mounted to the concrete wall and the_ seismic demand is enveloped at and above the building frequency.
Capacity; BSCav.2: Data was not available for this valve, but its body is not suspected to be cast iron.
BSCav.4&5: The wall mounted SV unit was tug tested and judged acceptable.
l
e Prairie Island Nuclear Generating Plant GIP R;v 2, Corrected,2/14/92 SCREENING EVALUATION WORK SHEET (SEWS)
Status: Yes Shoot 3 of 4 IDi SV 37022 ( Rev. 0 )
l Class : 8. Motor-Operated and Solenoid-Operated Valves l
Desenption : 121 CONT RM HNDLR OA SPLY STM EXCL B SV Building : AUX Floor El. : 761.00 Room, Row / Col: ON W SIDE WALL G.5/7.3 Manufacturer, Model, Etc. :
1 Evaluated by:
Mark McKeown Date:
t r
i Walter Djordjevic
Attachment:
Pictures f
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Prairie 1: land Nuclear Generating Plant GIP R;V 2. Corrected,2/14/92 i
SCREENING EVALU ATION WORK SHEET (SEWS)
Status: Yes Sheet 4 of 4 ID : SV 37022 ( Rev. 0 )
l Clars : 8. Motor-Operated and Solenoid-Operated Valves Descnption : 121 CONT RM HNDLR OA SPLY STM EXCL B SV Building : AUX Floor El. : 761.00 Room, Row / Col: ON W SIDE WALL G 5/7.3 Manufacturer, Model, Etc PJCIURES
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f, ;, ' ' :f SV 37022 l
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Northern Statee Power Company. Proer6e island Nuclear Generst6ng Plant GIP Rev 2, corrected,2/14/92 4
SCREENING EVALUATION WORK SHEET (SEWS)
Status: Yes Sheet 1 Of 11 10 : 181 ( Rev. 0 )
l Class : 20. Instrumentateun and Control Panels and Cabinets Desenpton : PROCESS PROTECTION RACK 181 j
Building : AUX l Floor Et : 735 00 1 Room. Row / Col: Control Room Manufacturer, Model. Etc. -
SEISMIC CAPACITY VS DEMAND
~
1.
Elevation where equ6pment receives seismic input 735.00 2.
Elevation of seismk: input below about 40' from grade (grade = 695.00)
Yes 3.
Equipment has fundamental frequency above about 8 Hz (est frequency = 11.00) 1'es 4.
Capacity based on:
1.00 ' Bounding Spectrum 5.
Demand based on:
1.00
- Design Basis Ground Response Spectrum 2.000 7
~
/
G LOG
~
0.100 i
i i
- i i ii e
i i
i i i ii 1.00 LOG Hz 100.00 Capacitj..... Demand F ile Record Capacity H \\QlPCIP\\ spectra des LabellBounding Spectrum Demand 1 H \\G.PiPROJ0040\\ spectra des MASS POINTSIN/AlBUILD'NGlGROUNDjDIRECTIONjHORIZONTAllRADI AL DISTIN/AlELEVATIONI695 00 Demand 2 H \\GIPiPROJ0040\\ spectra cos MASS POINTSIN/AIBUILDINGIGROUND]DIRECTIONIHORIZONTALl RAD; AL DISTIN/AIELEVATION!695 00 Does capacity exceed demand?
Y.as i
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4 Northem States Power Company. Pro 6ne island holoar Genersting Plant GlP Rev 2, Corrected,2/14/92 l
SCREENING EVALUATION WORK SH5ET (SEWS)
Status: Yes Sheet 2 of 11 i
ID : 181 ( Rev. 0 )
l Class : 20. Instrumentation and Control Panels and Cabinets
{
Desenption : PROCESS PROTECTION RACK 181 Building : AUX l Floor El. : 736 00 l Room. Row / Col: Control Room Manufacturer, Model, Etc.
CAVEATS. BOUNDING SPECTRUM l&C/BS Caveat 1. Earthquake Exoenence Equg. ent Class.
Yes I&C/BS Caveat 2 Computers and Programmable Controllers Evaluated Separately.
N/A IEC/BS Caveat 3. Stnp Chart Recorders Evaluated.
N/A
}
i l&C/BS Caveat 4 Structurel Adequate.
- Yes l&C/BS Caveat 5 Adjacent Cabinets or Panels Bolted Together.
Yes l&C/BS Caveat 6. Drawers or Equipment on Slides Restrained.
Yes l&C/BS Caveat 7. Doors Secured.
Yes ISC/BS Caveat 8 Sufficient Slack and Flexibiltty of Attacht1 Lines.
Yes l&C/BS Caveat 9 Adequate Anchorage.
Yes l&C/BS Caveat 10. Potential Chatter of Essential Relays Evaluated.
N/A I&C/BS Caveat 11. No Other Concerns.
Yes 1
is the intent of all the caveats met for Bounding Spectrum?
hs ANCHORAGE
- 1. The sizes and locations of anchors have been determined.
Yes
- 2. Appropriate equipment charactenstics have been determined (mass, CG, natural freq.,
Yes damping, center of rotahon).
- 3. The type of anchorage is covered by the GlP.
Yes
- 4. The adequacy of the anchorage installation hat, been evahated (weld quality and length, Yes nuts and washers, expansion anchor tightness, etc.)
- 5. Factors affecting anchorage capacity or margin of safety have been considered: embedment Yes' length, anchor spacing, free edge distance, concrete ?trongth! condition, and concrete cracking.
- 6. For bolted anchorages, any gaps under the base are less than 1/4, Yes 7, Factors affecting essential relays have been considered; gaps under the base, capacity N/A reductbn for expansion anchors.
- 8. The base has adequate stiffness arShe effect of prying action on anchors has been Yes considered.
- 9. The strength of the equipment base and the load path to the CG is adequate.
Yes
- 10. The adequacy of embedded steel, grout pads or large concrete pads have been evaluated.
N/A
- 11. The anchorage capacity exceeds the demand.
Yes Are anchorage requirements met?
hs omw-m.e-e,.--.--ye---e pe,-4+-
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Northom States Power Company. Prairk Island Nwloor Generstang Plant GIP Rev 2. Corrected,2/14/92 SCREENING EVALUATION WORK SHEET (SEWS)
Status Yes 1
Sheet 3 of 11 10 : 181 ( Rev. 0 )
l Class : 20. Instrumentation and Control Panets and Cabinets Desenption : PROCESS PROTECTION RACK 181 Buildeng : AUX l Floor El. : 735 00 l Room. Row / Col: Control Room Manufacturer, Model. Etc. -
INTERACTION EFFECTS
- 1. Soft targets are free from impact by nearby equipment or structures.
Yes
- 2. If the equipment contains sensitive relays, it is free from all impact by nearby equipment or N/A structures.
- 3. Attached lines have adequate flexibility.
Yes
- 4. Overhead equipment or distributun systems are not likely to collapse.,
Yes
- 5. No other adverse concems were found.
Yes e
is equipment free of interaction effects?
YIA
[31QUlEMENLSE18MLCALLY ADEQUATEZ Y.es C.QMMENIS SRT: W. Djordjevic (S&A) and G. Ridder (WPS) 5/23/94.
REF: NSP Dwg. NF 38300 27 Rev. H, NF 38315-9 Rev, H, NF.383131 Rev. HH & NF.39750 Rev. S Anchorage:
Connected in a 4 unit line-up of 1W1,1W2,181 and 102. Panels themselves are 90" tall,22"/ unit wide, and 30" deep. Each panel is anchored to a structural steel platform by 4 3/4" steel bolts inset 2" typ. from comers.
The platform is 17" high welded steel angle frame (MK lCS 1, ref.) anchored to floor by a 5/8" J bolt at each post (AB-C8). The frame support all four units and consists of 4x3x3/8" angle around the perimeter and 8 4x4x3/8" angle posts All cabinets are interconnected by internal botting.
According to GIP table C.1 1 and assuming the panels are 1/8" steel plate, the typical maximum mass per panel is, 3 x [2 x (90x22 + 22x30 + 30x90) x 1/8 /12^3) x 490 = 1140 lbs per panel.
1 Check support steel platform:
From SEWS 14MR, each post can resist a horizontalload of 2.1 kips when analyzed as a 17"long cantilever.
Since the platform has 8 legs, it can resist a horizontal seismic load of 8 x 2.1 = 16.8 kip, which is applied due to a seismic acceleration of, 16800 / (4 x 1140) = 3.68 G.
Given the applied spectral acceleration of 0.349 G in each horizontal direction and the SRSS rule of combining seismic loading, the platform's safety factor = 3.68 / (2^0.5 x 0.349) = 7.5.
Since, the capacity of the 3/4" steel to steel bolting (4 per panel) is greater that! the capacity of the 5/8" J-bolt anchorage to concrete (total of 8 for the platform), the anchorage evaluation will consider the J-bolt anchorage.
- Also, tne J bolts are embedded 9.5" which is < 16D = 10" and according to GIP the J botts have no tensile capacity, but there is an overtum moment, hence the anchorage analysis will consider a 1/2" J bolt instead of 5/8",
thereby meeting the intent of this anchorage caveat.
The attached anchorage evaluation show the J-bolts are adequate with a safety factor which is less than that of the platform, therefore the anchorage safety factor is govem by the J-bolts.
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~4 86erthem states Power c: ;:,,. Pro 6ete tenend he6ser Genereelne Plant GIP Rev 2, Corrected,2/14/92 i
SCREENING EVALUATION WORK SHEET (SEWS)
Status: Yes Sheet 4 of 11 10 : 181 ( Rev. O ;
l Class : 20. Instrumentaten and Control Panels and Cabinets Descapoon : PROCESW PROTECTION RACK 181 Su66 ding : AUX l Floor El. : 736 00 l Room, Row / Col : Control Room Manufacturer, Model Etc. :
I Seismic interaction-A generic issue at Prairie Island with open S-hooks throughout plant for hung overhead florescent lights. This
~'
should be dealt wh on a plant-wide basis. Work Order #9510032 was initiated to crimp the S-hooks on overhead light fixtures.
Also, seismic houwkeeping ir. control room was found to be adequate.
/@.L n/1/n' Date:
Evaluated by:
//~/0~ T T v
vl
Attachment:
ANCHOR Re e
~
Northem stetoe Power company. Pro 6fte leland Nucht Generoth::: Plant GIP Rev 2 Corrected,3/14/92 1
SCREENING EVALUATION WORK SHEET (SEWS)
Status: Yes Sheet 5 of 11 ID : 181 ( Rev 0 )
l Class : 20. InsVuitstation and Control Panels and Cabine.s Desenption : PROCESS PROTECTION RACK 181 Building : AUX l Floor El. : 735 00 l Room. Row / Col: Control Room Manufacturer, Model. Etc..
ANCHOR Report Earthquake t Response Spectrum : SSE Frequency : GIP. Flexible Percent Damping : GIP 5.00 SpectralValues :
prection Acceleration (g's) i North South 0 349 East West 0.349 Vertical 0.150 Angle (N S Direction makes with the X Axis): 0.00 Combination Criteria : SRSS Welshtu Number of Weights : 4 No Weight X
Y Z
1 1140.00 9.000 12.500 62.000 2
194E00 31.000 12.500 62.000 3
1140.00 a63.000 12 300 62.000 4
1140 00 75.000 12.500 62.000 Entces; Number of Extemal Forces : 0 Momentaj Number of External Moments : 0 Allowableal AnchoL Number of Anchor types : 1 Tension Shear Ultimate Ultimate Inter Inter Saf No.
Dia Manufact Product Tension Shear Coeff Coeff Fact
__1 1/2 Other J Bolt (90 6660.00 3330.00 1.00 0.30 1.00 deg)
{3ncrete :
t/itimate Stress : 3000.00 psi.
Reducten Factor: 0.85
~
~. -
Northem States Power Company. Pralrle letand Nuclear Generating Plant GIP Rev 2. Corrected,2/14/92 1
SCREENING EVALUATION WORK SHEET (SEWS)
Status: Yes Sheet 6 of 11 ID : 181 ( Rev. 0 )
l Class : 20. Instrumentation and Control Panels and Cabinets Desenption : PROCESS PROTECTION RACK 181 Building : AUX
( Floor El. : 735.00 l Room, Row / Col : Control Room Manufacturer, Model, Etc.
W1 Allowable Stress : 30600 psi.
Surfaces _
Number of Surfaces : 1 Surface Orientation Direction Direction Direction Comp Comp Comp No Nr Ny Nz 1
0.000 0.000 1.000 Anchor Pattern for Surface # 1 4
E t-X Legend for Anchor Patterns Anchor Bolts :
Concrete Lines:
Concreto Points : I f::___
Weld Lines :
[e __
GenadOL Anchor :
Number of Anchors : 8
l 1
Northem Statee Power Company. Pro 6 rte telend Nuclear Genersong Plant GIP Rev 2. Corrected,2/14/92 I
f.
SCREENING EVALUATION WORK SHEET (SEWS)
Status: Yes Sheet 7 of 11 10 : 181 ( Rev. 0 )
l Class : 20. Instrumentaten and Control nanels and Cabinets Desenpton : PROCESS PROTECTION RACK 181 Buildang : AUX l Floor El : 735 00 l Room, Row / Col: Control R'oom Manufacturer, Model, Etc.
Anch X
Y Z
Surf
'No.
id Coord Coord Coord Id i
1 1
~~ 0.000 0.000 0.000 1
2 1
28.000 0.000 0 000 1
3 1
56.000 0.000 0.000 1
4 1
84.000 0.000 0.000 1
5 1
84.000 25.250 0 000 1
6 1
56.000 25 250 0 000 1
l 7
1 28.000 25.250 0.000 1
8 1
0.000 25.250 0.000 1
Conctate Lines :
- of elements perline : 4 Number of Concrete Linen ; O Cancrete Points :
Number of Concrete Points : 8 X
Y Z
Surf Cone Pt No.
Coord Coord Coord Id Area 1
0.000
- 0.000 0.000 1
36.000 2
28.000-0.000 0.000 1
36.000 l 3 56.000 0.000 0.000 1
36.000 7
84.000 0.000 0.000 1
36.000 5
84.000 25.250 0.000 1
36.000 0
56.000 25 250 0.000 1
36.000 7
28.000 25.250 0.000 1
36.000 8
0.000 25.250 0.000 1
36.000 i
Weld Linen i
- of elements perline : 4 Number of Weld Lines : 0 Determination.otReductionfactoral Reduction Facte.. 'nput for Anchor # 1 Adequately Installed : Yes.
Embedment length : (27.25 in. Min Reqd. to achieve full capacity) := 0.50 in.
Gap at Threaded Anchor : 0.00 in.
Edge Distance Edge 1 : 4.38 in.
Crack Size : 0.000 in. - Cracks traverses thru installation Essential Relays in Cabinet : No Adequate Equipment Base Strength and Structural Load Path : Yes Embedment Steel and Pads Adequately Installed : Yes
'i
.i j
Northem Stoke Power Company. Pro 6th leland Nucker Generseng Plant GIP Rev 2. Corrected,2/14/92 i
SCREENING EVALUATION WORK SHEET (SEW 8)
Status: Yes i
Sheet 8 of 11 ID : 181 ( Rev. 0 )
l Class : 20. Instrumentaten and Control Panels and Cabinets Desenpton : PROCESS PROTECTION RACK 181 l'
Building : AUX l Floor El. : 735.00 l Room, Row / Col: Control Room Manufacturer. Model. Etc..
Reduction Factor input for Anchor # 2 Adequately Installed : Yes Embedment Length : (27.25 in. Min Reqd. to achieve full capacity) := 9.50 in.
Gap at Threaded Anchor: 0.00 in.
Edge Distance. Edge 1 : 4.38 in.
Crack Size : 0.000 in.. Cracks traverses thru installation Essential Relays in Cabinet: No Adequate Equipment Lase Strength and Structural Load Path : Yes Embedment Steel and Pads Acsquately installed : Yes Reduction Factor input for Anchor # 3 Adequately Instal:ed : Yes Embedment length : (27.25 in. Min Reqd. to achieve full capacity) := 9.50 in.
Gap at Threaded Anchor : 0.00 in.
Edge Distance. Edge 1 : 4.38 in.
Crack Size : 0.000 in.. Cracks traverses thru installation Essential Relays in Cabinet : No Adequate Equipment Case Strength s nd Structural Load Path : Yes Embedment Steel and Pads Adequately Installed : Yes Reduction Factor input fofAnchor # 4 Adequately Installed : Yes Embedment length : (27.25 in. Min Reqd. to achieve full capacity) := 9.50 in.
Gap at Threaded Anchor : 0.00 in.
Edge Distance. Edge 1 : 4.38 in.
Crack Size : 0 000 in. - Cracks traverses thru installation Essential Relays in Cabinet : No Adequate Equipment Base Strength and Structural Load Path : Yes Embedment Steel and Pads Adequately Installed : Yes Reduction Factorinput for Anchor # 5 Adequately Installed : Yes Embedment length : (27.25 in. Min Reqd. to achieve full capacity) := 9.50 in.
Gap at Threaded Anchor : 0.00 In.
Edge Distance. Edg31 : 4.38 in.
Crack Size : 0.000 in. - Cracks traverses thru installation Essential Relays in Cathnet : No =
Adequate Equipment Base Strength and Structural Load Path : Yes Embedment Steel and Pads Adequately Installed : Yes Reduction Factor input for Anchor # 6 Adequately Installed : Yes
j
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i
?
1 Northom Statae Power Company. Preifte latend Nucles Generating Plant GlP Roy 2 Corrected,2/14/98 J
SCREENING EV/st.UATION WORK SHEET (SEWS)
Status: Yes Sheet 9 of 11 10 : 181 g Rev. 0 )
l Class : 20. Instrumentaten and Control Panels and Cabinets i
Desenption : PROCESS PROTECTION RACK 181 Building : AUX l Floor El. : 735 00 l Room. Row / Col: Control Room
~ Manufacturer. Model. Etc..
Embedmont Length : (27.25 in. Min Reqd. to achieve full capacity) := 9.50 in.
Gap at Threaded Anchor : 0.00 in.
Edge Distance Edge 1 : 4.38in.
i Crack Size : 0.000 in.. Cracks traverses thru Installation Essential Relays in Cabinet: No Adequate Equipment Base Strength and Structural Load Path : Yes Embedmont Steel and Pads Adequately Installed : Ye:
Reduction Factorinput for Anchor # 7 Adequately Installed : Yes Embedmont Length : (27.25 in. Min P.eqd. to achieve full capacity) := 9.50 in.
Gap at Threaded Anchor : 0.00 in.
Edge Cistance Edge 1 : 4.38 in.
Crack Size : 0.000 in.. Cracks traverses thru installatiori Essential Relays in Cabinet : No Adequate Equipment Base Strength and Structural Load Path : Yes Embedmont Steel and Pads Adequately Installed : Yes Reducten Factorinput for Anchor # 8 4
Adequately Installed : Yes Embedment LenCth : (27.25 in. Min Reqd. to achieve full capacity) := 9.50 in.
Gap at Threaded Anchorf 0.00 in.
Edge Distance Edge 1 : 4.38 in, Crack Size : 0.000 in.. Cracks traverses thru Installation Essential Relays in Cabinet : No Adequate Equipment Base Strength and Structural Load Path : Yes Embedment Steil and Pads Adequately Installed : Yes Reduction Factors Data Current : Yes 1
Ane Psil/
Paltrl No ed Vall Valtr RT RN RL RG RS RE RF RC RR RP RB RM 1
1 2663 70 N/A
- 1.00 1 00 0 43 1.00 1 00 1 00 0 93 1.00 1 00 1.00 1.00 1.00 3082 98 N/A 1 00 1 00 1 00 1.00 1.00 1 00 0 m3 1 00 1.00 1 00 1.00 1.00 2
1 2663 70 N/A 1 00 1 00 0 43 1 OC 1 00 1.00 0 93 1 00 1.00 1.00 1.00 1.00 3082 98 N/A -
1 00 1 00 1 00 1 00 1 00 1 00 0 93 1 00 1.00 1 00 1 00 t.00 3
1 2663 70 N/A 1 00 1 00 0 43 1.00 1 00 1.00 0 93 1.00 1 00 1.00 1.00 1 00 3082 98 N/A 1 00 1 00 1 00 1.00 1 00 1 00 0 93 1 00 1 00 1.00 1.00 1 00 4
1 2663 70 N/A 1 00 1 04 0 43 1 00 1 00 1 00 0 93 1 00 1.00 1 00 1.00 1 00 3082 98 N/A 1 00 1 00 1 00 1 00 1 00 1 00 j 613 1.00 1 00 1 00 1.00 1.00 5
1 2663 70 N!A 1.00 1 00 0 43 1 00 1 00 1.00 f93 1 00 1 00 1 00 1.00 1 00 3082 98 N/A 1.00 1 00 1 00 1 00 1.00 1.00 0 93 1.00 1 00 1.no 1.00 1.00 3
1 2663 70 N/A 1 00 1.00 0 43 1 00 1 00 1 00 0 93 1 00 1.00 1.00 1,00 1 00 3082 93 N/A 1 00 1 00 1.00 1 00 1 00 1.00 0 93 1 00 1.00 1.00 1 00 1.00 7
1 2663 70 N/A 1 00 1 00 0 43 1.00 1 00 1.00 0 93 1.00 1 00 1 00 1 00 1.00 3082.98 N/A 1 00 1.00 1.00 1 00 1 00 1.00 0 93 1 00 1.00 1.00 1.00 1.00
._ 8 1
2663 70 N/A 1 00 1 00 0 43 1 00 1.00 1 00 0 93 1.00 1 00 1 00 1.00 1.00 '
3082 98 N'A 1 00 1 00 1 00 1 00 1 00 1 00 0 93 1 00 1.00 1 00 1.no 1.00
Northern steese Power Company. Pro 6rm letand Nuc6 ear Generseng Plant GIP Rev 2, Corrected,2/14/92 SCREENING EVALUATION WORK SHEET (SEWS)
Status: Yes Sheet 10 of 11 ID : 181 ( Rev. 0 )
l Class : 20. Instrumentaten and Control Panels and Cabinets Desenption : PROCESS PROTECTION RACK 101 Building : AUX l Floor El. : 735 00 l Room, stow / Col: Control Room Manufacturer, Model Etc. -
Leoant :
I N/A
- Not Applicable Pall
= Allowable Pull without Reduced inspection Vall
= Allowable Shear without Reduced inspectior Palir
= Allowable Pull with Reduced inspecton Vallr
= Allowable Shear with Reduced inspectd.
= Outlier X
= Reduction Factor Not Used RT
= Reduction Factor for Type of Anchorage RN
= Reduction Factor for Installation Adequacy RL
= Reduction Factor for Embedment RG_
= Reduction Factor tw Gap at An,chors RS a Reduction Factor for Spacing RE
= Reduction Factor for Edge Distarce RF
= Reduction Factor for Concrete Strength RC
= Reduction Factor for Concrete Cracks RR
= Reduction Factor for Essential Relays RP
= Reduction Facter for Base Stiffness and Prying Action RB
= Reduction Factor for Base Strength and Lead Path "RM
= Reduction Factor for Embed. Steel and Pads AnalyalS.ERAlllit.1 Analysis Performed : Yes Type of Analysis : Regular Spectral Accelerations (G's) l No NS E.W Vertical Safety Factor 1
0.349 0.140 0.060 7.615 2
-0.349
-0.140
-0.060 8.483 3
-0.349 0.140 0.060 7.615 4
0.349 0.140 0.060 8 483 _
5 0.349
- 0. t 40 0.060 7.607 6
-0.349 0.140
-0.060 8 497 7
0.349
' O.140
-0.060 8 497 8
0.349 0140 0.060 7.607 9
0.140 0.349 0.060 3 205 10
-0.140 0.349
-0.060 3.426 11 0.140
-0.349 0.060 3.196 12
-0.140 0.349
-0.060 3.440 13
-0.140 0.349 0.060 3.205 14 0.140
-0.349
-0.060 3.426 15 0.140 0.349
-0.060 3.440 16
-0.140
-0.349 0.060 3.196 17 0.140 0.140 0.150 6.793 18
-0.140
-0.140
-0.150 10556
__ _. ~
7
.f
'M' Northem States Power Company. Pro 6 rte le6end Nuotear Generat6ng Plant GtP Rev 2, Corrected,2/14/92
.)
SCREENING EVALUATION WORK SHEET (SEWE)
Status: Yes Sheet 11 of 11 10 : 181 ( Rev. 0 )
l Class : 20. Instrumentaten and Control Panels and Cabinets Desenpton : PROCESS PROTECTsON RACK 181 Build 6ng : AUX l Floor El. : 735.00 l Room, Row / Col: Control Room Manufacturer, Model, Etc. :
19
_ _ 0.140 0.140
-0.150 10.652 20
-0.140 4.140 0.150 6.793 21
-0.140 0.140 0.150 6.793 M
0.140
-0.140 0.150 10.556
~5 0.140 0.140 0.150 6.793 2
( 24
-0.140 0.140
-0.150 10.652 i
Minimum Safety Factor : 3.196 The anchorage can withstand 3.196 times greater seismic demand I-
j-Northern States Power Company. Prairie Island Nuclear Generating Plant GIP Rev 2, Corrected,2/14/92 SCREEK:NG EVALUATION WORK SHEET (SEWS)
Status: Yes Sheet 1 of 4
~
ID : 2R1 ( Rev. 0 )
l Class : 20. Instrumentation and Control Panels and Cabinets Desenption : PROCESS PROTECTION RACK 2R1 Building : AUX l Floor El. : 735.00 l Rt,om, Row / Col : Control Room Manufacturer, Model. Etc. -
SEISMIC CAPACITY V8 DEMAND 1.
Elevaton where equipment receives seismic input 735.00 2.
Elevation of seismic input below about 40' from grade (grade = 695.00)
Yes 3.
Equipment has fundamental frequency above about 8 Hz (est. frequency = 11.00)
Yes 4.
Capacity based on:
1.00
- BC,unding Spectrum i
5.
Demt.nd based on:
1.00
- Design Basis Ground Response Spectrum 8
2.000
~~~
/
G LOG
~
. ' '... * *,... ,,,,......--....,,,,...,,i...................
i i
i i i e iil i
i e
i i i ii 0.100 1.00 LOG Hz 100.00 Capacity..... Demand File Record Capacity H \\ GIP \\ GIP \\ spectra des Label l Bounding Spectrum Demand 1 H.\\0lP\\PROJ0040\\ spectra des MASS POINTSIN/AlBUILDINGl GROUND lDIRECTIONIHORIZONTAllRADI AL DISTlN/AJELEVATIONI695 00 Demand 2 H.\\GIPPROMuwpectra des MASS POINTS lN/AIBUILDINGl GROUND [ DIRECTION l HORIZONTAL lRADI AL DISTIN/Al ELEVATION 1695 00 Does capacity exceed demand?
Y.es i
j Northern States Power Company Prairie island Nuclear Generating Plant GIP Rev 2, Corrected,2/14/92 1
SCREENING EVALUATION WORK SilEET (SEWS)
Status: Yes Sheet 2 of 4 10 : 2R1 ( Rev. 0 )
l Class : 20. InstrumentPtion and Control Panels and Cabinets Desenption : PROCESS PROTECTION RACK 2R1 Building : AUX _
l Floor El. : 735.00 l Room, Row / Col: Control Room Manufacturer, Model Etc. -
CAVEATS BOUNDING SPECTRUM t
l&C/BS Caveat 1 - Earthquake Expenence EquipEent Class.
[_
Yes l&C/BS Caveat 2 Computers and Programmable Controllers Evaluated Sep trysieL _
N/A-l&C/BS Caveat 3 - Stnp Chart Recorders Evaluated.
N/A I&C/BS Caveat 4 Structural Adequate.
Yes l&C/BS Caveat 5 Adjacent Cabinets or Panels Bolted Together.
Yes l&C/BS Caveat 6 - Drawers or Equipment on Slides Restrained.
Yes l&C/BS Caveat 7 Doors Secured.
Yes l&C/BS Caveat 8 - Sufficient Slack and Flexibility of Attached Lines.
Yes l&C/BS Caveat 9 - Adequate Anchorage.
Yes l" CSS Caveat 10 - Potential Chatter of Essential Relays Evaluated.
N/A I&C/BS Caveat 11 - No Other Concerns.
Yes l
is the intent of all the caveats met for Bounding Spectrum?
Yes ANCHORAGE
- 1. The sizes and louons of anchors have been determined.
Yes
- 2. Appropnate equipment charactenstics have been determined (mass, CG, natural freq.,
Yes damping, center of rotation).
- 3. The type of anchorage is covered by the GIP.
Yes
- 4. The adequacy of the anchorage installation has been evaluated (weld quality and length, Yes nuts and washers, expansion anchor tightness, etc.)
- 5. Factors affecting anchorage capacity c margin of safety have been considered: embedment Yes' length, anchor spacing, free-edge distance, concrete strength / condition, and concrete cw.my R Foi :.9 d Enchorages, any gaps under the base are less than 1/4.
Yes i Fancm affecting essential relays have been considered: gaps under the base, capacity N/A ree on for expansion anchors.
I
- 8. The base has adequate stiffness and the effect of prying action on anchors has been Yes considered.
- 9. The strength of the equipment base and the load path to the CG is adequate.
Yes
- 10. The adequacy of embedded steel, grout pads or large concrete pads have been evaluated.
N/A
- 11. The anchorage capacity exceeds the demand.
Yes Are anchorage requirements met?
Y.01 l
4, Northem States Power Company. Prairie Island Nuclear Generating Plant GlP Rev 2. Corrected,2/14/92 SCREENING EVALUATION WORK SHEET (SEWS)
Status: Yes Sheet 3 of 4 10 : 2R1 ( Rev. 0 ) -
l Class : 20. Instrumentation and Control Panels and Cabinets Desenption : PROCESS PRO 1ECTION RACK 2R1 Building : AU'(
l Floor El. : 735.00 l Room. Row / Col: Control Room
_Manufgre, Model. Etc. :
INTERACTION EFFECTS -
~
- 1. Soft targets are free from impact by nearby equipment or structures.
Yes
- 2. If the equipment contains sensitive relays, it is free from allimpact by nearby equipment or N/A structures.
- 3. Attached lines have adequate flexibility.
Yi,s
- 4. Overhead equipment or distnbution systems are not likely to collapse.
Yes
- 5. No other adverse concems were found.
Yes la equipment free of interaction effects?
Yes
!!LEQUIPMENT SEISMICALLY ADEQUATE?
Yes COMMENTS SRT: F. Stille (S&A) and G. Gore (NSP) - 8/23/95.
REF: NSP Dwg. NF-38300-27 Rev. H, NF-38315-9 Rev. H, NF-383131 Rev. HH & NF-39750 Rev. S Anchorage:
Connected in a 4-unit line-up of 2Y1,2Y2,2R1 and 2R2. The panels themselves are 90" tall,22"/ unit wide, and l
30" deep. Each panelis anchored to a structural steel platform by 4 bolts, one per comer.
The platform is 17" high welded steel angle frame (MK ICS 1, ref.) anchored to floor by a 5/8" J-bolt at each post (AB-C8). The frame supportall four units and consists of 4x3x3/8" angle around the perimeter and 8 - 4x4x3/8" angle posts. All cabinets are interconnected by intemal botting.
l This line-up is the same as the line up which contains panet 181, therefore for additional notes and anchorage evaluation see the SEWS for 181. Also, for photos see the SEWS for 2R2.
4 Seismic Interaction:
There is a generic issue at Prairie Island with open S-hooks throughout plant for hung overhead florescent lights.
This should be deait with on a plant wide basis. Work Order #9510032 was initiated to crimp the S-hooks on
)
overhead light fixtures.
Also, there is a fire extinguisher on a small shallow hook in close proximity to units, but it is far enough from unit 2R1 to be of no consequence.
[
Evaluated by:
Date:
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3 Northem States Power Company. Praerle Island Nuclear Generating Plant GIP Rev 2, Corrected,2/14/92 SCREENING EVALUATION WORK SHEET (SEWS) -
Status: Yes Sheet 4 of 4 10 : 2R1 ( Rev, 0 )
l Class : 20. Instrumentation and Control Panels and Cabinets Description : PROCESS PROTECTION RACK 2R1 Building : AUX l Floor El. : 735,00 l Poom, Row / Col: Control Room Manufacturer, Model Etc. :
1 4
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Northern Statae Power Company. Prairie leland Nuclear Generating Plant GIP Rev 2 Corrected,2/14/92 SCREENING EVALUATION WORK SHEET (SEWS)
Status: Yes Sheet i of 12 10 : 145 041 ( Rev. 0 )
l Class : 5. Honzontal Pumps Desenption : 11 CHG PUMP Building : AUX l Floor El. : 695.00 l Room. Row / Col: H.5/6.6 Manufacturer, Model. Etc. :
SEISMIC CAPACITY VS DEMAND 1.
Elevation where equipment receives seismic input 695.00 2.
Elevation of seisme input below about 40' from grade (grade = 695.00)
Yes 3.
Equipment has fundamental frequency above about 8 Hz (est. frequency = 33.00)
Yes 4.
Capacity based on:
1.00
- Bounding Spectrum 5.
Demand based on:
1.00
- Design Basis Ground Response Spectrum A
2.000
~
/
G L00
~
'~,,i..................................
0.100 i
i i
i i i i iI i
i i
i i e ii 1.00 LOG Hz 100.00 Capacity.... Demand File riecord Capacity H \\GIPGIPupectra des Labe48ounding Spectrum Demand 1 H WIP\\PROJ0040\\ spectra des MASS U
POINTSIN!Al BUILDING l GROUND l DIRECTION 1 HORIZONTAL lRADI AL DISTlN/AJELEVATIONl695.00 Demand 2 H.\\0lPPROJ0040\\ spectra. des MASS POINTSIN!AIBUILDINGlOROUNDlDIRECTIONjHORIZONTALlRADI AL DISTlN/AlELEVATIONI695 00 Does capacity exceed demand?
Y.es l
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Northem States Power Company. Prairle island Nuclear Generating Plant GIP Rev 2, Corr 3cted,2/14/92 SCREENING EVALUATION WORK SHEET (SEWS)
Status: Yes Sheet 2 of 12 ID : 145-041 ( Rev. 0 )
l Class : 5. Honzontal Pumps Descripton : 11 CHG PUMP Building : AUX l Floor El. : 695.00 l Room, Row / Col: H.5/6.6 Manufacturer, Model Etc. :
CAVEATS. BOUNDING SPECTRUM HP/DS Caveat 1 - Earthquake Expenence Equipment Class.
Yes HP/BS Caveat 2 - Onver and Pump on Rigid Skid.
Yes HP/BS Caveat 3 - Thrust Bearings in Both Axial Directons.
Yes HP/BS Caveat 4 - Check of Long Unsupported Piping.
Yes HP/BS Caveat 5 - Base Vibration isolation System Checked.
N/A HP/BS Caveat 6 - Sufficient Slack and Flexibihty of Attached Lines.
Yes HP/BS Caveat 7 - Adequate Anchorage.
Yes HP/BS Caveat 8 Potential Chatter of Essential Relays Evaluated.
N/A-HP/BS Caveat 9 No Other Concerns.
Yes
- Is the intent of all the cavests met for Bounding Spectrum?
Yes ANCHORAGE
- 1. The stzes and locations of anchors have been determined.
Yes
- 2. Appropnate equipment charactenstics have been determined (mass, CG, natural #eq.,
Yes damping. center of rotation).
- 3. The type of anchorage is covered by the GlP.
Yes
- 4. The adequacy of the a3chorage installation has been evaluated (weld quality and length, Yes nuts and washers, expansion anchor tightriess, etc.)
- 5. Factors affecting anchorage capacity or margin of safety have been considered: embedment Yes' length, anchor spacing, free-edge distance, concrete strength / condition, and concrete cracking.
- 6. For bolted anchorages any gaps under the base are less than 1/4.
Yes
- 7. Factors affectng essential relays have been considered; gaps under the base, capacity N/A reduction for expansion anchors.
- 8. The base has adequate stiffness and the effect of prying action on anchors has been Yes considered.
- 9. The strength of the equipment base and the load path to the CG is adequate.
Yes
- 10. The adequacy of embedded steel. grout pads or large concrete pads have been evaluated.
Yes
- 11. The anchorage capacity exceeds the demand.
Yes Are anchorage requirements met?
Yes Y
1 Northem States Power Company. Prairie island Nuclear Genersting Plant GlP Rev 2, Corrected,2/14/92 SCREENING EVALUATION WORK SHEET (SEWS)
Status: Yes Sheet 3 of 12 ID : 145-041 ( Rev 0 )
l Class : 5. Honzontal Pumps Desenpton : 11 CHG PUMP Build:ng: AUX l Floor El. : 695.00 l Room, Fww/ Col: H.5/6.6 Manufacturer, Model, Etc. :
INTERACTION EFFECTS
- 1. Soft targets are free from impact by nearby equipment or structures.
Yes
- 2. If the equipment contains sensitive relays, it is free from all Impact by nearby equipment or N/A structures.
- 3. Attached lines hnve adequate flexibility.
Yes
- 4. Overhead equipment or distnbution systems are not likely to collapse.
Yes
- 5. No other adverse concems were found.
Yes is equipment free of interaction effects? -
Y.es IS EQUIPMENT SEISMICALLY ADEQUATE?
Yes CQlMIENTS SRT: W. Djordjevic (S&A) and G. Ridder (WPS) - 5/26/94 REF: Ajax Dwg No. 2553 (NSP Dwg. X HIAW 1-49, Rev. A.); Pioneer Dwgs: NF-38313-1HH, NF-38308-1, NF-38308-2 4
Anchorage:
The charging pump is anchored onto a concrete pad (4'-8" wide x 13'-0" long x 26" high) by 8 1/8" J. Bolts (4 per side). The pad is dowelled into the concrete foundation slab which is at elevation 673'-0". The motor unit is anchored by shear blocks instead of alignment pins which is judged to be acceptable. The pump assembly weights are; Pump 4700 #, Vari Drive 3225 #, Motor 500#, and skid 1200#.
The J-bolt have an edge distance of 3-1/4" which is less than the minimum allowable distance of 4.5"(4D);
however the anchor analysis conservatively uses a smaller J-bolt (3/4") thereby meeting the intent of the this caveat.
This Anchor analysis used an enveloping set of Suction and Discharge Nozzle loads which were tabulated (see attachment). This analysis is conservative and demonstrates that the anchorage meets the intent of the GIP. The weights used in the anchor analysis are; Pump 4700 #, Vari Drive 3225 #, Motor 500#, and skid 1200#,
Evaluated by:
Date:
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Attachment:
Pictures
Attachment:
Nozzle Load Summary
Attachment:
ANCHOR Report
_ _ - ____ __ -_ - _ _____---- _.__.___..-_ __~_-..
I Northern States Power Company. Prairie island Nuciwar Generating Plant GIP Rev 2, Corrected,2/14/92 SCREENING EVALUATION WORK SHEET (SEWS)
Status: Yes Sheet 4 of 12 ID : 145-041 ( Rev. 0 )
l Class : 5. Honzontal Pumps Desenption : 11 CHG PUMP Building : AUX l Floor El. : 695.00 l Room, Row / Col: H.5/6.6 Manufacturer, Model. Etc. '
I PICTURES i
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I Fig.1: Charging Pump (145-041)
Fig.2: Charging Pump (145-041) Detail 1
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3 Noethern States Power Company. Praerte island Nuclear Generath.g Plant GIP Rev 2. Corrected,2/14/92 SCREENING EVALUATION WORK SHEET (SEWS)'
Sheet 5 of 12 Status: Yes 10 : 145-041 ( Rev. 0 )
l Class : 5. Honzontal Pumps Desenpton : 11 CHG PUMP Building : AUX l Floor El. : 695.00 l Room, Row / Col: H.5/6.6 Manufacturer, Model, Etc. :
Nozzle Load Summary l
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Northern States Power Company Prairle loland Nuclear Generating Plant GIP Rev 2. Corrected,2/14/92 SCREENING EVALUATION WORK SHEET (SEWS)
Status: Yes Sheet 6 of 12 10 : 145-041 ( Rev. 0 )
l Class : 5. Honzontal Pumps Desenption : 11 CHG PUMP Building : AUX l Floor El. : 695.00 l Room, Row / Col : H.5/6.6 Manufacturer, Model. Etc..
ANCHOR Report Earthquake ;
Response Spectrum : SSE Frequency: GIP Rigid Percent Damping : GIP - 5.00 Spectral Values :
Direction Acceleration (g's)
North - South 0.225 East - West 0.225 Vertical 0.150 Angle (N S Direction makes with the X Axis) : 0.00 Combination Criteria : SRSS Weights :
Number of Weights : 4 No Weight X
Y Z
1 3225.00 130.000 33.000 50.000 2
500.00 24.500 18.250 23.500 3
1200.00
'f5.500 25.750 4.000 4
4700.00 60.000 19.000 47.000 Entcas :
Number of Extemal Forces : 2 No Fx Fy Fz X
Y Z
1 2.32E+002 3.72E+002
-2.03E+002 145.000 26.000 50.000 2
-4.66E+002 2.87E+002 7.43E+002 145.000 42.500 50.000 Moments Number of Extemal Moments : 2 No Mx My Mz 1
1.15E+003 7.82E+003 1.43E+004
-2 5.78E+003 3.40E+004 2.13E+004 Allowables Anchor :
Number of Anchor types : 1
Northern States Power Company Prairie Island Nuclear Generating Plant GIP Rev 2 Corrected,2/14/92 SCREENING EVALUATION WORK SHEET (SEWS)
Status: Yes Sheet 7 of 12 10 : 145-041 ( Rev. 0 )
l Class : 6. Honzontal Pumps Desenption : 11 CHG PUMP Building : AUX l Floor El. : 695.00 l Room, Row / Col: H.5/6.6 Manufacturer, Model, Etc. -
Tension Shear Ultimate Ultimate inter inter Saf No.
Dia Manufact Product Tension Shear Coeff Coeff Fact 1
3/4 Other J-Bolt (90 7510.00 1.00 0.30 1.00 deg) 15030.00 Concrete :
Ultimate Stress : 3000.00 psi.
Reduction Factor : 0.85 4
WckL Allowable Stress : 30600 psi.
SuffACAS.;
Number of Surfaces : 1 Surface Orientation Direction Direction Direcuon Comp Comp Comp No Nx Ny NZ 1
0.000 0.000 1.000 4
Anchor Pattem for Surface # 1 7
O O
O X
Legend for Anchor Pattems i
l
Northern States Fower Company. Prairie loland Nuclear Generating Plant GIP Rev 2, Corrected,2/14/92 9CREENING EVALUATION WORK SHEET (SEWS)
Status: Yes Sheet 8 of 12 ID : 145-041 ( Rev. 0 )
l Class : 5. Henzontal Pumps Desenption : 11 CHG PUMr) building : AUX l Floor El. : 695.00 l Room, Row / Col : H.5/6.6 Manufacturer, Model, Etc.
Anch0r Bolts :
Concrete Unes :
r._ _ __
Concrete Points: l Weld Lines :
Gnometry :
hltt10C Number of Anchors : 8 i Anch X
Y Z
Sud No.
Id Coord Coord Coord Id 1
1 24.500 1.063 0.000 1
2 1
59.000 1.063 0.000 1
3 1
94.000 1.063 0.000 1
4 1
129.000 1.063 0.000 1
5 1
129.009 50.437 0.000 1
6 1
94.000 50.437 0.000 1
7 1
59.000 50.437 0.000 1
8 1
24.500 50.437 0.000 1
Concrete Lines :
- of etcments per line : 5 Number of Concrete Lines : 4 i
Start l
Start Start End End End St Line
~
No X-Cooid Y-Coord Z Coord X-Coord Y-Coord Z-Coord Id Width 1
0.000 1.500 0.000 151.000 1.50u 0.000 1
3.000 2
0.000 50.000 0.000 151.000 50.000 0.000 1
3.000 3
1.500 3.000 0.000 1.500 48.500 0.000 1
3.000 4
149.500 3.000 0.000 149.500 48.500 0.000 1
3.000 Concrete Point Number of Concrete Points : 0 Weld Lines :
- of elements per line : 5 Number of Weld Lines : 0 Determination of Redus1[Qn.factotlu
Northern $tates Power Company. Prairie I;ta..d Nuclear Generating Plant GIP RIV 2, Corrected,2/14/92 3
- SCREENING EVALUATION WORK SHEET (SEWS)
Status: Yes Sheet 9 of 12 10 : 145-041 ( Rev. 0 )
l Class : 5. Honzontal Pumps Desenpton : 11 CHG PUMP Building : AUX l Floor El. : 695.00 l Room. Row / Col: H.5/6.6 Manufacturer. Model. Etc. :
Reduction Factor !nput for Anchor # 1 l
Adequately Installed : Yes Embedment Length : (40.88 in. Min Reqd. to achieve full capacity) :=22.00 in.
Gap at Threaded Anchor: 0.13 in.
Edge Distance - Edge 1 : 3.25in..
Crack Size : 0.000 in. - Cracks traverses thru installation Essential Relays in Cabinet : No Adequate Equipment Bace Strength and Structural Load Path : Yes Embedment Steel and Pads Adequately Installed : Not Applicable Reduction Factor input for Anchor # 2 Adequately Instatied : Yes Embedment Length : (40.88 in. Min Reqd. to achieve full capacity) :=22.00 in.
Gap at Threaded Anchor : 0.13 in.
Edge Distance - Edge 1 : 3.25 in.
Crack Size : 0.000 in. - Cracks traverses thru installation 4
Essential Reiays in Cabinet : No Adequate Equipment Base Strength and Structural Load Path : Yes Embedment Steel and Pads Adequately Installed : Not Applicable Reduction Factor input forJnchor # 3 Adequately Installed : Yes Embedment length : (40.88 in. Min Reqd. to achieve full capacity) :=22.00 in.
Gap at Threaded Anchor : 0.13 in.
Edge Distance - Edge 1 : 3.25 in.
Crack Size : 0.000 in. - Cracks traverses thru installation Essential Relays in Cabinet : No Adequate Equipment Base Strength and Structural Load Path : Yes Embedment Steel and Pads Adequately Installed : Not Applicable Reduction Factor input for Anchor # 4 Adequately installed : Yes Embedment Length : (40.88 in. Min Reqd. to achieve full capacity) :=22.00 in.
. Gap at Threaded Anchor : 0.13 in.
Edge Distance - Edge 1 : 3.25 in.
Crack Size : 0.000 in. - Cracks traverses thru installation.
Essential Relays in Cabinet : No -
)
Adequate Equipment Base Strength and Structural Load Path : Yes Embedment Steel and Pads Adequately Installed : Not Applicable Reduction Factor input for Anchor # 5 Adequately installed : Yes 1
Embedment length : (40.88 in. Min Reqd. to achieve full capacity) :=22.00 in.
1
. - ~ -
Northem States Power Company. Preirte island Nucteer Generating Plant GIP Rev 2< Corrected,2/14/92 SCREENING EVALUATION WORK SHEET (SEWS)
Status: Yes Sheet 10 of 12 1D : 145&1 ( Rev. 0 )
l Class : 5. Honzontal Pumps Desenption : 11 CHG PUMP Building : AUX l Floor El. : 695.00 l Room. Row / Col: H.5/6.6 Manufacturer, Model. Etc. '
Gap at Threaded Anchor : 0.13 in.
- y Edge Distance - Edge 1
- 3.25 in.
Crack Size : 0.000 in. - Cracks traverses thru installation
. Essential Relays in Cabinet : No Adequate Equipment Base Strength and Structural Load Path : Yes Embedment Steel and Pads Adequately Installed : Not Applicable Reduction Factor Input for Anchor # 6 Adequately Installed : Yes
- Embedment Length : (40.88 in. Min Reqd. to achieve full capacity) :=22.00 in.
Gap at Threaded Anchor: 0.13 in.
Edge Distance - Edge 1 : 3.25 in.
Crack Size : 0.000 in. - Cracks traverses thru installation Essential Relays in Cabinet : No Adequate Equipment Base Strength and Structural Load Path : Yes Embedment Steel and Pads Adequately Installed : Not AppEcable Reduction Factor input for Anchor # 7 Adequately Instalied : Yes Embedment Length : (40.88 in. Min Reqd. to achieve full capacity) :=22.00 in.
Gap at Threaded Anchor: 0.13 in.
Edge Distance - Edge O 3.25 in.
Crack Size : 0.000 in. - Cracks traverses thru Installation Essential Relays in Cabinet : No Adequate Equipment Base Strength and Structural Load Path : Yes Embedment Steel and Pads Adequately Installed : Not Applicable Reduction Factor input for Anchor # 8 Adequately installed : Yes Embedment Length : (40.88 in. Min Reqd. to achieve full capacity) :=22.00 in.
+
Gap at Threaded Anchor : 0.13 in.
Edge Distance - Edge 1 : 3.25 in.
Crack Size : 0.000 in, - Cracks traverses thru installation Essential Relays in Cabinet : No Adequate Equipment Base Strength and Structural Load Path : Yes Embedment Steel and Pads Adequately Installed : Not Applicable Reduction Factors Data Current : Yes -
Anc Pall /
Palfr/
No ld Vall Valir RT RN RL RG RS RE RF RC RR RP RB RM 1
1 5126 94 N/A 1.00 1.00 0 60 1.00 1.00 0.62 0 93 1.00 1.0C 1.00 1.00 1.00 1710 34 N/A 1.00 1.00 1.00 1.00 1.00 0.25 0 93 1.00 1.00 1.00 1.00 1.00 I
_2 1
5126 94 N/A 1.00 1.00 0 60 1.00 1.00 0 62 0 93 1.00 1.00 1.00 1.00 1.00 1710 34 N/A 1.00 1.00 1.00 1.00 1.00 0.25 0 93 1.00 1.00 1.00 1.00 1.00 3
1 5126 94 N/A 1 00 1.00 0 60 1.00 1.00 0 62 0 93 1.00 1.00 1.00 1.00 1.00
j.-
Northern States Power Company. Prairie Island Nuclear Generating Plant GIP Rev 2, Corrected,2/14/92 SCREENING EVALUATION WORK SHEET (SEWS)
Status: Yes Sheet 11 of 12 ID.145441 ( fox 0 )
l Class : 5. Honzontal Pumps Descnoten : 1' CHG PUMP Building: AUX l Floor El. : 695.00 l Room, Row / Col: H.5/6.6 Manufacturer, Mooe:, Etc. -
1710 34 N/A 1.00 1.00 1.00 1 00 1.00 0 25 0 93 1.00 1.00 1.00 1.00 1.00 4
1 5126 94 N/A 1.00 1.00 0 60 1 00 1.00 0 62 0 93 1.00 1.00 1.00 1.00 1.00 1710 34 N/A 1.00 1.00 1.00 1.00 1.00 0.25 0 93 1.00 1.00 1.00 1.00 1.00 5
1 5126 94 N/A 1 u0 1.00 0 60 1.00 1.00 0 62 0 93 1.00 1.no 1.00 1.00 1.00 1710 34 N/A 1.00 1.00 1.00 1.00 1.00 0 25 0 93 1.00 1.00 1.00 1.00 1.00 6
1 5126 94 N/A 1.00 1.00 0 60 1.00 1.00 0 62 0 93 1.00 1.00 1.00 1.00 1.00 1710 34 N/A 1.00 1.00 1.00 1.00 1.00 0 25 0.93 1.00 1.00 1.00 1.00 1.00 7
1 5126 94 N/A 1.00 1 00 0 60 1.00 1.00 0 62 0 93 1.00 1.00 1.00 1.00 1.00 1716.34 N/A 1.00 1 00 1.00 1.00 1.00 0.25 0 93 1.00 1.00 1.00 1.00 1.00 8
1 5126 94 N/A 1.00 1.00 0 60 1.00 1.00 0 62 0 93 1.00 1.%
1.00 1.00 1.00 17'.0 34 N/A 1.00 1 00 1.00 1.00 1.00 0 25 0 93 1.00 1.00 1.00 1.00 1.00 LAGBQd' N/A
= Not Applicable Pall
= Allowable Pull without Reduced Inspection Vall
= Allowable Shear without Reduced innpection Palir
= Allowable Pull with Reduced inspection Vallr
= Allowable Shear with Reduced inspection
= Outlier -
X
= Reduction Factor Not Used RT
= Reduction Factor for Type of Anchorage RN
= Reduction Factor for installation Adequacy RL
= Reduction Factor for Embedment RG
= Reduction Factgr for Gap at Anchors RS
= Reduction Factor for Spacing RE
= Reduction Factoi for Edge Distance RF
= Reduction Factor for Concrete Strength RC
= Reduction Factor for Concrete Cracks RR
= Reduction Factor for Essential Relays
'RP
= Reduction Fcetor for Base Stiffness and Prying Action
_R B
= Reduction Factor for Base Strength and Load Path RM
= Reduction Factor for Embed. Steel and Pads Analysis Results :
Analysis Performed : Yes Type of Analysis : Regular Spectral Accelerations (G's)
No N-S E-W Vertical Safety Factor 1
0.225 0.090 0.060 5.283 2
-0.225
-0.090
-0.060 5.436 3
-0.225 0.090 0.060 5.121 4
0.225
-0.090
-0.060 5.621 5
0.225
-0.090 0.060 5.510 6
-0.225 0.090
-0.060 5.219 _
7 0.225 0.090-
-0.060 5.405 8
-0.225
-0.090 0.060 5.375 i
e.
i Northern Statoo Power (,ompany. Prair6e Island Nuclear Generating Plant GIP Rev 2, Corrected,2/14/92 SCREENING F. VALUATION WORK SHEET (SEWS)_
Status: Yes Sheet 12 of 12 ID : 145441 ( Rev. 0 's l Class : 5. Honzontal Pumps Desenpuon : 11 CHG PUMP Building : AUX l Floor El. : 695.00 l Room, Row / Col: H.5/6.6 Manufacturer, Model, Etc. :
9 0.090 0.225 0.060 4.577 10
-0.090
-0.225
-0.060 5.316 11 0.090
-0.225 0.060 5.157 12
-0.090 0.225
-0.060 4.828 13
-0.090 0.225 0.060 4.603 14 0.090
-0.225
-0.060 5.383 15 0.090 0.225
-0.060 4.741 16
-0.090
-0.225 0.060 5.093 17 0.090 0.090 0.150 8.382 18
-0.090
-0.000
-0.150 11.201 19 0.090 0.090
-0.150 9.834 20-
-0.090
-0.090 0.150 9.542 21
-0.090 0.090 0.150 8.454 22 0.090
-0.090
-0.150 11.501 23 0.090
-0.090 0.150 9.843 24
-0.090 0.090
-0.150 9.769 Minimum Safety Factor: 4.577 The anchorage can withstand 4.577 times greater seismic demand 4
a 4
4' Northom States Power Company. Pro 6 rte telend Nuclear Generating Plant GIP Rev 2. Corrected,2/14/92 SCREENING EVALUATION WORK SHEET (SEWS)
Status: Yes Sheet 1 of 11 ID : 145-201 ( Rev. 0 )
l Class : 5. Honzontal Pumps Desenption : 11 TD AFW PUMP Building : TURB l Floor El. : 695.00 l Room, Row /Coi: F.5/8.3 Manufacturer, Model. Etc. -
SEISMIC CAPACITY V8 DEMAND 1.
Elevation where equipment receives seismic input 695.00 2.
Elevation of seismic input below about 40' from grade (grade = 695.00)-
Yes 3.
Equipment has fundamental frequency above about 8 Hz (est. frequency = 33.00)
Yes 4.
Capacity based on:
1.00
- Bounding Spectrum 5.
Demand based on:
1.00 ' Design Basis Ground Response Spectrum 2.000
~-~
/
G LOG
^
.. "..... - ~... '....,, ' ~.....
+
0.100 il
. ~ "' "" ~ ~ I ~ " 'i""'I"I"Iii i
i e
i i i i i
1.00 LOG Hz 100.00 Capacity.... Demand File Record Capacrty H \\GIPiGIPupectra des Label l Bounding Spectrum 4.
Demand 1 H.GPPROJ0040\\ spectra. des MASS
[
POINTS lN/Al BUILDING l GROUND lDIRECTIONjHORIZONTALlRADI AL DISTlN/Al ELEVATION 1695.00 Demand 2 H4tPiPROJ0040\\ spectra des MASS POINTS!N/Al BUILDING l GROUND l DIRECTION]HORIZONTAllRADI AL DISTIN/AIELEVATION!695.00 Does capacity exceed demand?
Y.ca J'
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Northom States Powee Corr pony. Pratrie Island Nuclew Generating Plant GIP Rev 2, Corrected,2/14/92 SCREENING EVALUATION WORK SHEET (SEWS)
Status: Yes Sheet ? of 11 ID : 145 201 ( Rev. 0 )
. l Class : 5. Honzontal Pumps Description : 11 TD AFW PUMP Building : TURB l Floor El. : 695.00 l Room, Row / Col: F.5/8.3 Manufacturer, Model, Etc. :
CAVEATS BOUNDING SPECTRUM HP/BS Caveat 1 - Earthquake Exponence Equipment Class.
Yes HP/BS Caveat 2 Driver and Pump on Regid Skid.
Yes HP/BS Caveat 3 - Thrust Beanngs in Both Axial Directions.
Yes HP/BS Caveat 4 Check of Long Unsupported Piping.
Yes HP/BS Caveat 5 - Base Vibration isolation System Checked.
Yes HP/BS Caveat 6 Sufficient Slack and Flexibility of Attached Lir'es.
Yes HP/BS Caveat 7 Adequate Anchorage.
Yes HP/BS Caveat 8 - Potential Chatter of Essential R91ays Evaluated.
N/A HP/BS Caveat 9 No Other Concems.
Yes
- is the intent of all the caveats met for Bounding Spectrum?
Y31 ANCHORAGE
- 1. The sizes and locations of anchors have been determined.
Yes
- 2. Appropnate equipment characteristics have been determined (mass, CG, natural freq.,
Yes damping, center of rotation).
- 3. The type of anchorage is covered by the GIP.
Yes
- 4. The adequacy of the anchorage installation has been evaluated (weld quality and length, Yes nuts and washers, exp5hslon anchor tightness, etc.)
5 Factors affecting anchorage capacity or margin of safety have been considered: embedment Yes*
length, anchor spacing, free-edge distance, concrete strength / condition, and concrete
~'
cracking.
- 6. For bolted anchorages, any gaps under the base are less than 1/4, Yes
- 7. Factors affecting essential relays have been considered; gaps under the base, capacity N/A reduction for expansion anchors.
- 8. The base has adequate stiffness and the effect of prying action on anchors has been Yes considered.
y 3
- 9. The strength of the equipment base and the load path to the CG is adequate.
Yes
- 10. The adequacy of embedded steel, grout pads or large concrete pads have been evaluated.
Yes
- 11. The anchorage capacity exceeds the demand.
Yes Are anchorage requirements met?
Y.es v.
w
Northern 9tetoe Power Company. Prairie telend Nuclear Generating Plant GIP Rev 2 Corrected,2/14/92 L
SCREENING EVALUATION WORK SHEET (SEWS)
Status: Yes Sheet 3 of 11 10 : 145 201 ( Rev. 0 )
l Class : 5. Honzontal Pumps Desenpton : 11 TD AFW PUMP
~duilding : TURB l Floor El. : 695.00 l Room, Row / Col: F.5/8.3 Manufacturer, Model, Etc. '
INTERACTION EFFdCTS
' 1. Soft targets are free from impact by nearby equipment or structures.
Yes
- 2. If the equipment contains sensitive relays, it is free from all impact by nearby eqtipment or N/A structures.
- 3. Attached dnes have adequate flexibility.
Yes
- 4. Overhead equipmeat or distnbution systems are not iskely to collapse.
Yes
- 5. No other adverse concems were found.
Yes
^
Is equipment free of interact %n effects?
Yes IS EQUIPMENT SEISMICALLY ADEQUATE?
Yes GQMMENTS SRT: W. Djordjevic (S&A), M. McKeawn (NSP), F. Stille (S&A) and G. Gore (NSP) - 11/21/93.
REF: Dresser ind. (Pacific Pumps) Dwgs 46580, Pioneer Dwgs NF 382216, NF 38221-4, NF 38221-9 Anchorage:
4 The pump is anchored onto a concrete pad (3'-6" wide x 14'-4" long x 20" high) by 8 - 3/4" J.Botts (4 per side) and the pad is dowelled into the concrete foundation slab. The J-bolts have a short side edge distance of 4-1/8" and long side edge distance of 10" on 3" high grout pad. The pump assembys weights are: Pump 4150 lbs, Turbine:
1585 lbs, Skid 1650 lbs and Oil Cooler 120 lbs.
Also, the J-bolt are embedded 8.5" which is less than the minimum allowable embedment of 12" (16D); however the anchor analysis conservatively uses a smaller J-bolt (1/2") thereby meeting the intent of the this caveat.
The piping nozzle loads used in the anchorage analysis were developed in calculation 93C2807-C-016. This analysis is conservative and demonstrates that the anchorage meets the intent of the GIP.
Evaluated by:
Date:
? $nn Hilaim s-Attachrent: Pictures
Attachment:
ANCHOR Report
i f'
Northern States Power Comp:ny. Prairi31:lind Nucle:r Genereung PI:nt GIP Rev 2 Corrected,2/14/92 SCREENING EVALUATION WORK SHEET (SEWS)
Status: Yes Sheet 4 of 11 ID : 145-201 ( Rev. 0 )
l Class : 5. Honzontal Pumps
]
Desenption : 11 TD AFW PUMP Building : TURB l Floor El. : 695.00 l Room, Row / Col: F.5/8.3 Manufacturer, Model, Etc.
ElCIllBES 1
L l
j
. }f d'f'I,
+
l !
1; s :.1, j_
j l [t
'i 1,
i t
j Steam Driven Auxiliary Feedwater Pump (145 201)
I
+
f1 l
l
-, _ =
Northem States Power Company. Prettio leland Nuclear Generstmg Plant GIP Rev 2, Corrected,2/14/92 SCREENING EVALUATION WORK SHEET (SEWS)
Status: Yes
+.
Sheet 5 of 11 10 : 145 201 ( Rev. 0 ) -
l Class : 5. Honzontal Pumps Desenption : 11 TO AFW PilMP -
Building : TURB l Floor 8. i 696.00 l Room, Row / Col: F.5'8.3 Manufacturer, Model, Ett'.
ANCHOR Repor' Earthquake :
Response Spectrtm : SSE Frequency:GtP Rigid Percent Damphig : GIP - 5.00 SpectralValues :
Direction Acceleration (g's)
North South 0.225 East - Wa 0.225
~
l Vertical 0.150 Angle (N-S Direction mues with *e X Axis): 180.00 Pombination Criteria : Si,3S Weights :
Number of Weights : 4 l
Z No Weight X
Y,
20 000 1
4150.00 63.000 19.880 2
1585.00 120.000 19.875 20.000 3
1850.00
-f6.500 19.875 2.500 4
120.00 54.000 31.000 8.000 Forcesj j
Number of Extemal Forces : 4 1
No Fx Fy Fz X
Y Z
1 1.10E+001 2.32E+002
-9.10E+001 17 000 53.000 18.000 2
163E+003_ 5.58E+002
-3.33E+003 21.000 5.000 18.000 3-1.35F4002
-7.40E+001 2.22E+002 74.000 18.000 37.000 4
1.20E+002
-6.90E+001
-2.94E+002 110.000 18.000 37.000 Moments :
Number of Extemal Moments : 4 No i Mx My Mz 1
-2.40E+001
-3.6CE+001 7.48E+003 2
-3.80E+004 1.61 E+005 3.33E+004 1
3 4.68E+003 3.18E+003 1.98E+003 4
1.63E+003 3.23E+003 1.32E+003 Alinwables :
Northem States Power Company. Prairie Island Nuclear Generating Plant GIP Rev 2, Corrected,2/14/92 SCREENING EVALUATION WORK SHEET (SEWS)
Status: Yes Sheet 8 of 11 ID : 145-201 ( Rev. 0 )
l Class : 5. Honzontal Pumps Desenption : 11 TD AFW PUMP Building : TURB l Floor El. : 695.00 l Room, Row / Col: F.5/8.3 Manufacturer, Model, Etc.
AnchoI; Number of Anchor types : 1 Tension Shear Urimate Ultimate inter Inter Saf No.
Dia Manufact Product Tension Shear Coeff Coeff Fact 1
1/2 Other J-Bolt (90 6660.00 3330.00 1.00 0.30 1.00 deg)
ConCittill Ultimate Stress : 3000.00 psi.
Roduction Factor : 0.85 Weld:
Allowable Stress
- 30600 psi.
Surfaces :
Number of Surfaces : 1 Surface Orientation Direction Direction Direction Comp Comp Comp-No Nx A Ny NZ 1
0.000 0.000 1.000 Anchor Pattem for Surface # 1 4
w w
w m
a m
X Legend for Anchor Patterns
Northern States Power Company Prairie letand Nuclear Generating Plant GIP Rev 2, Corrected,2/14/92 SCREENING EVALUATION WORK SHEET (SEWS)
Status: Yes Sheet 7 of 11 10 : 145-201 ( Rev. 0 )
l Class : 5. Honzontal Pumps Descnotion : 11 TO AFW PUMP Building : TURB l Floor El. : 695.00 l Room, Row /Cc': F.5/8.3 Manufacturer, Model, Etc. -
Anchor Bolts:
,fg]
Concrete Unes:
Concrete Points:
Weld Unes :
Ej
.i Geometry.;
Anchor :
Number of Anchors : 8 Anch X
Y Z
Surf No.
Id Coord Coord Coord Id 1
1 6.000 1.500 0.000 1
2 1
53.000 1.500 0.000 1
3 1
100.000 1.500 0.000 1
4 1
147.000 1.500 0.000 1
5 1
147.0004 36.750 0.000 1
6 1
100.000 36.750 0.000 1
7 1
53.000 36.750 0.000 1
8 1
6.000 36.750 0.000 1
l Concrete Lines :
- of elements per line : 10 Number of Concrete Unes : 4 Start Start Start End End End Sf Line No X-Coord Y-Coord Z Coord X-Coord Y Coord Z-Coord k.
W dth 1
0.000 0.000 0.000 153.000 0.000 0.000 1
3.000 2
153.000 0.000 0.000 153.000 39.750 0.000 1
3.000 3
153 000 39.750 0.000 0.000 39.750 0.000 1
3.000 4
0.000 39.750 l
0.000 0.000 0.000 0.000 1
3.003 Concrete Points :
Number of Concrete Points : 0 Weld Liner
- of elements per line : 4 Nutrcer of Weld Lines : 0 Datermination of Reduction Factors :
L Northorn States Power Company o Prairk Island Nuclear Generating Plant GIP Rev 2 Corrected,2/14/92 -
SCREENING EVALUATION WORK SHEET (SEWS)
Status: Yes Sheet 8 of 11 ID : 145 201 ( Rev. 0 )
l Class : 5. Honzontal Pumps Desenption : 11 TD AFW PUMP -
Building : TURB l Floor El. : 695.00 l Room, Row l Col : F.5/8.3 Manufacturer, Model, Etc..
Raduction Factor input for Anchor # 1 Adequately Installed : Yes Embedment Length : (27.25 in. Min Reqd, to achieve full capacity) := 8.50 in.
Gap at Threaded Anchor : 0.00 in.
Edge Distance - Edge 1 : 4.13 in.
Crack Size : 0.000 in. - Cracks traverses thru installation Essential Relays in Cabinet : No Adequate Equipment Base Strength and Structural Load Path : Yes
' Embedment Steel and Pads Adequately Installed : Yes Reduction Factorinput for Anchor # 2 Adequately Installed : Yes Embedment Length : (27.25 in. Min Reqd. to achieve full capacity) := 8.50 in.
Gap at Threaded Anchor : 0.00 in.
Edge Distance - Edge 1 : 4.13 in.
Crack Size : 0.000 in. - Cracks traverses thru Installation Essential Relays in Cabinet : No Adequate Equipment Base Strength and Structural Load Path : Yes Embedment Steel and Pads Adequately Installed : Yes Reduction Factorinput for Anchor # 3 4
Adequately installed : Yes Embedment Leng',h : (27.25 in. Min Reqd. to achieve full capacity) := 8.50 in.
Gap at Threaded Anchor : 0.00 in.
Edge Distance - Edge 1 : 4.13 in.
Crack Size : 0.000 in. - Cracks traverses thru Installation Essenital Relays in Cabinet : No Adequate Equipment Base Strength and Structural Load Path : Yes
- Embedment Steel and Pads Adequately installed : Yes Reduction Factorinput for Anchor # 4 Adequately Installed : Yes Embedment Length : (27.25 in. Min Reqd. to achieve full capacity) := 8.50 in.
Gap at Threaded Anchor : 0.00 in.
Edge Distance - Edge 1 : 4.13 in.
Crack Size : 0.000 in. - Cracks traverses thru installation EYential Relays in Cabinet : No AJequate Equipment Base Strength and Structural Load Path : Yes Embedment Steel and Pads Adequately Installed : Yes Reduction Factor input for Anchor # 5 Adequately Installed : Yes Embedment Length : (27.25 in. Min Reqd. to achieve full capacity) := 8.50 in.
i'
Northom Statee Power Company. Preifte Island Nuclear Generating Plant GIP Rev 2, Corrected,2/i4/92 SCREENING Et ALUATION WORK SHEET (SEWS)
Status: Yes Sheet 9 of 11 10 : 145 201 ( Pev. 0 )
l Class : 5. Honzontal Pumps Desenption : 11 TO AFW PUMP Building : TURB l Floor El. : 695.00-l Room, Row / Col: F.5/8.3 Manufacturer Model, Etc. -
Gap at Threaded Anchor : 0.00 in.
Edge Distance - Edge 1 : 4.13 in.
Crack Size : 0.000 in. - Cracks traverses thru Installation Essentia* Relays in Cabinet : No Adequate Equipment Base Strength and Structural Load Path : Yes.
Embedrrnnt Stee! and Pads Adequate 5/ Installed : Yes Reduction Factor input for Anchor # 6 Adequately Installed : Yes Embedment length : (27.25 in. Min Reqd. to achieve full capacity) := 8.50 in.
Gap at Threaded Anchor : 0.00 in.
Edge Distance - Edge 1 : 4.13 in.
Crack Size : 0.000 in. - Cracks traverses thru installatim Essential Relays in Cabinet : No Adequate Equipment Base Strength and Structural Load Path : Yes Embedment Steel and Pads Adequately Installed : Yes Reduction Factor input for Anchor # 7 Adequately Installed : Yes Embedment Length : (27.25 in. Min Reqd. to achieve full capacity) := 8.50 in.
Gap at Threaded Anchor: 0.00 in.
' Edge Distance - Edge 1 :1,13 in.
Crack Size : 0.000 in. - Cracks traverses thru installation Essential Relays in Cabinet : No Adequate Equipment Base Strength and Structural Load Path : Yes Embedment Steel and Pads Adequately Installed : Ye?
Reduction Factor input for Anchor # 8 Adequately Installed : Yes Embedment length : (27.25 in. Min Reqd. to achieve full capacity) := 8.50 in.
Gap at Threaded Anchor : 0.00 in.
Edge Distance - Edge 1 : 4.13 in.
Crack Size : 0.000 in. - Cracks traverses thru installation Essential Relays in Cabinet : No Adequate Equipment Base Strength and Structural Load Path : Yes Embedment Steel and Pads Adequately installed : Yes Reduction Factors Data Current : Yes Anc paw Paltr/
I No ld Vall Vallr RT RN RL RG RS RE RF RC RR RP RB RM 1
1 2026 03 N/A 1.00 1.00 0 40 LOO 1.00 0 82 0 93 1.00 1.00 1.00 1.00 1.00 2148 84 N/A 1 00 1.00 1.00 1.00 1.00 0 89 0 93 1.00 1.00 1.00 1.00 1.00 2
1 2026 03 N/A 1.00 1.00 0 40 1.00 1.00 0 82 0 93 1.00 1.00 1.00 1.00 1.00 2748 84 N/A 1.00 1 00 1.00 1 00 1.00 0.89 0.93 1.00 1 00 1.00 1.00 1.00 3
1 2026 03 N/A 1.00 1 00 0 40 1.00 1.00 0 82 0 95 1.00 1.00 1.00 i 1.00 1.00
~
Northern States Power Company. Preitte Island Nuclear Generating Plant GIP R;v 2, Corrected,2/14/92 l
SCREENING EVALUATION WORK SHEET (SEWS)
Status: Yes Sheet 10 of 11 ID : 145 201 ( Rev. 0 )
l Claas : 5. Honzontal Pumps Desenption : 11 TD AFW PUMP Building : TURB l Floor El. : 695.00 l Room, Row / Col: F.5/8.3 Manufacturer, Model Etc. '
2748 84 N/A 1.00 1 00 1.00 1.00 1.00 0 89 0 93
'. 00 1.00 1.00 1.00 1.00 4
1 2026 03 N/A 1 00 1 00 0 40 1 00 1.00 0 82 0 93 1.00 1.00 1.00 1.00 1.00 2748 84 N/A 1 00 1.00 1 00 1 00 1.00 0.89 0 93 1.00 1.03 1.00 1.00 1.00 6
1 2026 03 N/A 1 00 1 00 0 40 1.00 1 00 0 82 0 93 1.00 1.00 1.00 1.00 1 00 2148 84 N/A 1.00 1 00 1 00 1 00 1.00 0 89 0 93 1.00 1.00 1.00 1.00 1.00 6
1 2026 03 N/A 1.00 1.00 0 40 1 00 1 00 0 82 0 93 1.00 1 00 1.00 1.00 1.00 2148 84 N/A 1 00 1.00 1.00 1 00 1.00 0 89 0 93 1.00 1.00 1.00 1.00 1.00 7
1 2026 03 N/A 1 00 1.00 0 40 1.00 1.00 0 82 0 93 1.00 1.00 1.00 1.00 1.00 2748 84 N/A 1,00 1.00 1.00 1.00 1.00 0 89 0 9:e 1.00 1.00 1.00 1.00 1.00 8
1 2026 03 N/A 1 00 1 00 0 40 1.00 1.00 0 82 0 93 1.00 1.00 1.00 1.00 1.00 2748 84 N/A 1.00 1.00 1.00 1 00 1 00 0 89 0 93 1.00 1.00 1.00 1.00 1.00 Legend; N/A
= 6'" Apphcable Pall
= Allowable Pull without Reduced insoection Vall
= Allowable Shear without Reduced Inspection Palle
= Allowable Pull with Reduced Inspection Varir
= Allowable Shear with R0duced lnopection
= Outher X
= Reduction Factor Not Used RT
= Reduction Factor for Type of Anchorage RN
= Reduction Factor for Installation Adequacy RL
= Reduction Factor for Embedment
~
= Reduction Factor for Gap at Anchors RS
= Reduction Factor for Spacing RE
= Reduction Factor for Edge Distance RF
= Reduction Factor for Concrete Strength RC
= Reduction Factor for Concrete Cracks RR
= Reduction Factor for Essential Relays RP
= Reauction Factor for Base Stiffness and Prying Action RB
= Reduction Factor for Base Strength and Load Path RM
= Reduction Factor for Embed. Steel and Pads Analy1ls Results :
Analysis Performed : Yes Type of Analysis : Regular Spectral Accelerations (G's)
No NS EW Vertical Safety Factor 1
0.225 0.090 0.060 12.065 2
--0.225
-0.090
-0.060 10.065 3
-0.225 0.090 0.060 10.358
)
4 0.225
-0.090
-0.060 11.986 5
0.225
-0.090 0.060 11.948 6
-0.225 0.090
-0.060 10.358 l
7 0.225 0.090
-0.060 12.279 8
-0.225 0.090 0.060 10.065
(
l L
Northom States Power Compasty. Protrie island Nuclear Genersong Plant GIP Rev 2, Corrected,2/14/92
~
SCREENING EVALUATION WORK SHEET (SEWS)
Status: Yes Sheet 11 of 11 i
10 : 145-201 ( Rev. 0 )
l Class : 5. Honzontal Pumps Desenptum : 11 TD AFW PUMP -
cuilding : TURB l Floor El. : 695.00 l Room, Row / Col: F.5/8.3 Manufacturer, Model, Etc.
9 0.090 0.225 0.060 10.084 10
-0.090
-0.225
-0.060 10.420 11 0.090
-0.225 0.060 9.739 12
-0.090 0.225
-0.060 11.128 13
-0.090 0.225 0.060 9.544 14 0.090 n.225 0.060 11.216 15 0.090 0.225
-0.060 11.924 16
-0.090
-0.225 0.060 9.191 17 0.090 0.090 0.150 15.632 18
-0.090
-0.090
-0.150 20.740 19 0.090 0.090
-0.150 24.571 20-
-0.090
-0.090 0.150 14.415 21
-G.090 0.090 0.150 14.385 22 0.090
-0.090
-0.150 23.112 23 0.099 0.090 0.150 15.617 24
-0.090 0.090
-0.150 21.344 Minimum Safety Factor: 9.191 The anchorage can withstand 9.191 tiraes greater seismic demand
+
f
Northem States Power Company. Prairie bland Nuclear Generating Plant GIP RCv 2, Corrected 2/14/92 OUTLIER SEISMIC VERIFICATION SHEET (OSVS)
Sheet 1 of 1 ID. 31 (Rev. 0) l Class : 20. Instrumentation and Control Panels and Cabinets
~Asenpton : CONTROL PANEL B 1 C
Building : AUX l Floor E!. : 735.00 l Room, Row / Col: Control Room
- 1. OUTLIER ISSUE DEFINITION 1 Mechanical and Electrical Eautoment
- a. Identify all the screening guidelines which are not met. (Check more than one if several guidelines could not be satisfied.)
Capacity vs. Demand Caveats Anchorage Seismic Interaction X
Other b.
Describe all the reasons for the outlier (i.e., if all the listed outlier issues were resolved, then the signatories would consider this item of equipment to be verified for seismic adequacy).
The control room ceiling is an outlier due to the aluminum diffussers which pose a personnel hazard, 2JEOPOSED METHOD OF OUTLIER RESOLUTION fontional) a.
Defined proposed method (s) for rescNing outlier.
' Tie wrap (plastic lines) are a reasonable fix for this situation.
4 b.
Provide information needed to implement proposed method (s) for resolving outlier (e 9., estimate of fundamental frequency).
L. CERTIFICATION:
The information on this OSVS is, to the best of our knowledge and belief, correct and accurate, and resolution of the outfier issues listed on the previous page will satisfy the requirements for this item of equipment to be verified for seismic adequacy:
Approved by:
Date:
i 7
s A
H+-w
- - - _ = _.
i
.'s Northom stem.e Power company. PraMe lotend Nuoleer Genero#ns Plant GtP Rev 2. Corrected,2/14/92 i
SCREENING EVALUATION WORK SHEET (SEWS)
Status: No i
Sheet 1 of 13 ID : B.1 ( Rev. 01 l Class : 20. Instrumentaten and Control Panels and Cabinets Desenpton : CONTROL PANEL B 1 Budding: AUX l Floor El. : 735.00 l Room. Row / Col: Control Room i
Manufacterer, Model, Etc. -
SEISM 6C CAPACITY VS DEMAND i
1.
Elevaten where equipment receives seisme input 735.00 2.
Elevaton of seisme input below about 40' from grade (grade = 695.00)
Yes 3.
Equ6pment has fundamental frequency above about 8 HZ (est. frequency = 11.00)
Yes 4.
Capacity based on:
1.00
- Bounding Spectrum 5.
Demand based on:
1.00
- Design Basis Ground Response Spectrum i
2.000 t
/
G
~
LOC
+.
0.100 e,,,,
i i
i i i i iI e
i i i e ii 1.00 LOG Hz 100.00 Capacity..... Demand Fi:e Record
, Capacity H 4tPCIP\\ sped e des Label l Bounding Spectrum Dernand 1 H O!PPROJ0040cectre des MASS POINTSIN/Al BUILDING lGROUNDIDIRECTION} HORIZONTAL lRADI A DISTlNlAlELEVATIONf695 00 Demand 2 H WIPPROJ0040\\ sprites ces VASS f>OINTSIN'AIBUILDINGlGROUNDIDIRECTIONl HORIZONTAL lRADI e l DISTlN/Al ELEVATION!695 00,
l Does ca nacity exceed <1emand?
Ysa
,. ~.,,.
t l,
l Northem States Power Company. Pro 6ne island Nuclear Generet6ng Plant GIP Rcv 2, Corrected,2/14/92 SCREENING EVALUATION WORK SHEET (SEWS)
Status: No Sheet 2 of 13 ID : B 1 ( Rev. 0 )
l Class : 20. Instrumentation and Control Panels and Cabinets i
Desenption : CONTRoi PANEL B 1 Buildito : AUX l Floor El. : 735 00 l Room, Row / Col: Control Room Manufacturer, Model, Etc..
CAVEATS BOUNDING SPECTRUM
~
l&C/BS Caveat 1. Earthquake Experience Equipment Class.
Yes I&C/BS Caveat 2 Computers and Programmable Controllers Evaluated Soparately.
Yes l&C/BS Caveat 3 - Stnp Chart Recorders Evaluated Yes l&C/BS Caveat ti - Structural Adequate.
Yes l&C/BS Cavea(UJpynt Cabinets or Panels Bolted Together.
Yes l&C/B"; Caveat 6 - brr,wers or Equipment on Slides Restrained.
Yes l&C/BS Caveat 7. (Ioors Secured.
Yes l&C/BS Caveat 8 Sufficient Slack and Flexibility of Attached Lines.
Yes 3C/BS Caveat 9 a Adequate Anchorage.
Yee l&C/BS C2veat 10 Potential Chatter of Essential Relays Evaluated N/A l&C/BS Caveat 11. No Other Concerns.
Yes is the intent of all the caveats met for Bounding Spectrum?
Yet ANCHOMOE
- 1. The stzes and locations of anchors have been determined.
Yes
- 2. Appropnate equipment charactenstics have been determined (7nass, CG, natural freq.,
Yes
_ damping, conter of rotation).
- 3. The type of anchoragdh covered by the GIP.
Yes
- 4. The adequacy of the anchorage installation has been evaluated (weld quahty and length, Yes nuts and washers, expansion snchor tightness, etc.)
- 5. Factors affecting anchorage capacity or margin of saWy nave been considered: embedment Yes' length, anchor spacing, free-edge distance, concrete suongth/ condition, and concrete cracking.
6 For bolted anchorages, any gaps under the base are less than 1/4.
Yes
- 7. Factors affecting essential relays have been considered: gaps under the base, capacity N/A reduction for expansion anchors.
- 8. The base has adequate stiffness and the effect # 1 rying &ction on anchors has been Yes considered.
- 9. The strength of the equipment base and the load path to the CG is adequate.
Yes
- 10. The adequacy of embedded steel, grout pads or large concrete pads have been evaluated.
N/A
- 11. The anchorage capacity exceeds the demand.
Yes Are anchorage requirements met?
Yfts l
l I
1
f NorWwm Statee Power Company Pen 6 rte leland Nuclear Generating Plant GIP Rev 2 Corrected,2/14/92 SCRELNING EVALUATION WORK SHEET (SEWS)
Status: No Sheet 3 of 13 ID : 81 ( Rev. 0 )
l Class : 20. Instrumentation and Control Panels and Cabinets Desenption : CONTROL PANEL B 1 Building : AUX l Floor El. : 735.00 l Room. Row / Col: Control Room l
Manufactu,er, Model. Etc..
P i
INTERACTION EFFECTS l
~
- 1. Son targets are free from impact by nearby equipment or structures.
Yes
- 2. If the equipment contains sonsttive relays, it is free from all impact by nearby equipment or N/A structures.
- 3. Attached lines have adequate flexibility.
Yes
- 4. Overhead equipment or distnbution sys' ems are not likely to collapse.
No
- 5. No other adverse concerns were found.
Yes is equipment free of interaction effects?
HQ i
ULEQUlEMENIRi&MiGALLY ADEQUAIE2 No COMMF.NIS SRT: W. Djordjevic (S&A) and G. Ridder (WPS) 5/23/94.
REF: NSP Dwg. NF 383131 Rev. HH, NF 39750 Rev. S & NF 38300 27 Rev. H.
Capacity:
Benchboard instrumentation was spot-checked and found to be properly installed.
BSCav.5: All cabinets are interconnected by intemal botting.
Anchorage:
Panel B 1 is part of the the Main Control benchboard "A" F". The panels,124" tall, are anchored to structural steel platforms by 6 3/8" steel bolts (3 on front and 3 on back) per bay. The platforms,17" high welded steel angle frames, are welded by 1/4" fillets 2"long and 12" on center to steel floor plate which runs along the front and rear of the benchboard. The steel floor plate,1/2" thick by 4.5" wide, is anchored into the concrete floor by 5/8" J-bolts (AB-C8) 12" on center. Also, the center benchboard posts (the posts which support the face of the benchboards) are weld to local floor plates which are anchored to ine concrete floor by 2 1/2" cinch anchors (one on each side of the post).
Each bay is approximately 60" wide, therefore, according to GIP table C.1 1 the typical maximum mass le 3300 lbs (see SEWS for panel A).
i The attached anchorage analysis considers the anchorage between the supporting platform and the concrete floor (i.e. 5/8" Dotts) of one bay as representaM of the complete beachboard. Also, the J-bolts are embedded 9.5" which is < 16D = 10", hence the anchorage analysis will consider a 1/2" J-bolt instead of 5/8", thereby meeting the intent of this anchorage caveat.
For the capacity evaluations of the support platform. platform welding to plate and plate capacity and the anchorage between the benchboard and the support platform see the SEWS for panel A.
.The anchorage evaluation concludes that the benchboard is adequately anchored with a significant safety factor l
which is governed by the anchorage between the benchboard and the supporting platform.
Northem States Power Company. Pro 6tte taland Nuclear Genereelne Meat GIP Rev 2, Corrected,2/14/92 SCREENING EVALUATION WORK SHEET (SEWS)
Status: No Sheet 4 of 13 10 : B 1 ( Rev. 0 )
l Class : 20. Instrumentation and Control Panels and Cabinets Description : CONTROL PANEL B 1 Building : AUX l Floor El. : 735.00 l Room, Row / Col: Control Room l
Manufacturer, Model. Etc. :
Seismic Interaction:
The control room ceiling is an outlier due to Aluminum diffussers vthich pose personnel hazard. Tie wrap (plastic lines) are a reasonable fix for this situation.
Also, there is a generic issue at Prairie Island with open S-hooks throughout plant for hung overhead florescent lights. This should be dealt with on a plant wide basis. Work Order #9510032 was initiated to crimp the S-hooks on overhead light fixtures.
Finally, seismic housekeeping in the control room was found to be adequate.
4 1
Evaluated by:
/
Date:
'9 y7/W
' Y-E- /0 ~ 9 S' r7
Attachment:
Pictures
Attachment:
ANCHOR Report e
l
l
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1 Northern St:t:s Power Company. Proins 1:l:nd Nuct er G:nercting PI:nt GIP Rev 2, Corrected,2/14/92 SCREENING EVALUATION WORK SHEET (SEWS)
Status: No l
l Sheet 5 of 13
{
i 10 : B-1 ( Rev. 0 )
l Class : 20. Instrumentation and Control Panets and Cabinets i
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Desenption : CONTROL PANEL B 1 f
j Building : AUX l Floor El. 735.00 l Room, Row / Col: Control Room l
Manufacturer, Model. Etc.
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l North m St:tse Power Company. Prains Island Nucizer G:nsreting Plant GIP Rev 2, Correc'3d,2/14/92 l
SCREENING EVALUATION WORK SHEET (SEWS)
Status: No I
Sheet 6 of 13 l
ID : B 1 ( Rev. 0 )
l Clas* : 20. Instrumentation and Control Panels and Cabinets Desenption : CONTROL PANEL B 1 l
Building : AUX l Floor El. : 735.00 l Room, Row / Col : Control Room Manufacturer, Model. Etc.
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Northom Stateo Power Company. Proene beland Nuclear Generating Plant GIP Rev 2, Corrected,2/14/92 SCREENING EVALUATION WORK SHEET (SEWS)
Status: No Sheet 7 of 13 ID : B 1 ( Rev. 0 )
l Class : 20. Instrumentation and Control Panels and Cabinets Desenption : CONTROL PANEL B 1 Butiding : AUX l Floor El. : 735.00 l Room. P.ow/ Col : Control Room Manufacturer, Model, Etc.
4 ANCHOR Report Earthquaka :
Response Spectrum : SSE Frequency : GtP Flexible Percent Damping : GIP 5.00 SpectralValues :
Direction Acceleration (g's)
North. South 0.349 i
East. West 0349 Vertical 0.150 Angle (N S Direction makes with the X Axis): 0.00 Combination Criteria : SRSS WalShtU Number of Weights : 1 No Weight X
Y Z
1 3300.00 30.000 24.500 79.000 Entcau Number of External Forces : 0 Moments.;
Number of Extemal Moments : 0 Allowabitu Anchor :
j Number of Anchor types : 1 Tension Shear Ultimate Ultimate inter Inter Saf No.
Dia Manufact Product Tension Shear Coeff Coeff Fact i
1/2 Other J-Bolt (90 6660.00 3330.00 1.00 0.30 1.00 deg)
Concrete :
Ultimate Stress : 3000.00 psi.
Reduction Factor : 0.85 Wald; Allowable Stress : 30600 psi.
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Northem States Power Company. Praine latand Nuclear Genersung Plant GIP RCv 2. Corrected,2/14/92 SCREENING EVALUATION WORK SHEET (SEWS)
Status: No Sheet 8 of 13 ID : B 1 ( Rev. 0 )
l Class : 20. Instrumentation and Control Panels and Cabinets Desenption : CONTROL PANEL B 1 Building : AUX l Floor Ell: 735.00 l Room, Row / Col : Control Room Manufacturer, Model, Etc.
- i Sudacts.J Number of Surfaces : 1 Surface Orientation Direction Direction Direction Comp Comp Comp No Nx Ny Nz 1
0.000 0.000 1.000 Anchor Pattern for Surface # 1 0
X Legend for Anchor Patterns Anchor Bolts :
Concreto Lines : I
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Concrete Points:
(__ _ _
Weld unes:
Geomet0C Anchor :
Number of Anchors : 10
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Northom States Power Company. Proine lolar.d Nuclear Generst6ng Plant GIP Rev 2, Corrected,2/14/92 SCREENING EVALUATION WORK SHEET (SEWS)
Status: No Sheet 9 of 13 ID : B 1 ( Rev. 0 )
l Class : 20. Instrumentation and Control Panels and Cabinets Desenption : CONTROL PANEL B 1 Building : AUX l Floor El. : 73550 l Room. Row / Col: Control Room Manufacturer, Model, Etc. -
Anch X
Y Z
Surf i
No.
id Coord Coord Coord id 1
1 6.000 2.000 0 000 1
_ __2 1
18.000 2.000 0.000 1
3 1
30.000 2.000 0.000 1
4 1
42.000 2.000 0.000 1
5 1
54.000 2.000 0.000 1
6 1
54.000 47.000 0.000 1
7 1
42.000 47.000 0.000 1
3 8
1 30.000 47.000 0.000 1
9 1
18.000 47.000 0.000 1
10 1
6 000 41.000 0.000 1
Concrete Linen _
- of elements per line : 5 Number of Concrete Lines : 4 Stari Start Start End End End St Line No X-Coord Y-Coord Z-Coord X Coord Y-Coord Z-Coord Id Width 1
0 000 1.500 0 000 60 000 1.500 0.000 1
3.000 2
58.500 0 000 0 000 58.500 49.000 0.000 1
3.000 3
60 000 47.5tfD 0000 0.000 47.500 0 000 1
3.000 4
1.500 49 000 0.000 1.500 0.000 0.000 1
3.000 Concrete Points :
Number of Concrete Points : 0 Weld Lines :
- of elements perline : 4 Number of Weld Lines : 0 Detttmination of Reduction Factors 1 Reduction Factor input for Anchor # 1 Adequate!y Installed : Yes Embedment Length : (27.25 in. Min Reqd. to achieve full capacity) := 9.50 in.
Gap at Threaded Anchor : 0.00 in.
Edge Distance. Edge 1 : 4.38 in.
Crack Size : 0.000 in.
Cracks traverses thru installation Essential Relays in Cabinet : No Adequate Equipment Base Strength and Structural Load Path : Yes Embedment Steel and Pads Adequately Installed : Yes Reduction Factor input for Anchor # 2 Aciequately Installed : Yes
Northom States Power Coms,any. Preerte telend Nuclear Generating Plant GIP Rev 2. Corrected,2/14/92 SCREENING EVALUATION WORK SHEET (SEWS)
Status: No Sheet 10 of 13 10 : B 1 ( Rev. 0 )
l Class : 20. Instrumentaten and Control Panels and Cabinets _
Desenpton : CONTROL PANEL B 1 Building : AUX l Floor El. : 735.00 l Room, Row / Col: Control Room Manufacturer, Model, Etc. -
Embedment length : (27.25 in. Min Reqd. *o achieve full capacity) := 9.50 in.
Gap at Threaded Anchor : 0.00 in.
Edge Distance - Edge 1 : 4.38 in.
Crack Size : 0.000 in.
Cracks traverses thru installation Essential Relays in Cabinet: No Adequate Equipment Base Strength and Structural Load Path : Yes Embedmont Steel and Pads Adequately Installed : Yes Reduction Factor input for Anchor # 3 Adequately Installed : Yes Embedment length : (27,25 in. Min Reqd. to achieve full capacity) := 9.50 in.
Gap at Threaded Anchor : 0.00 in.
Edge Distance Edge 1 : 4.38 in.
Crack Size : 0.000 in.
Cracks traverses thru installation Essential Relays in Cabinet: No Adequate Equipment Base Strength and Structural Load Path : Yes Embedment Steel and Pads Adequately Installed : Yes Reduction Factor input for Anchor # 4 Adequately Installed : Yes Embedment Length : (27.25 in. Min Reqd. to achieve full capacity) := 9.50 in.
Gap at Threaded Anchor
- 0.00 in.
Edge Distance Edge 1 : 4.38 in.
Crack Size : 0.000 in.
Cracks traverses thru installation Essential Re'ays in Cabinet : No Adequate Equipment Base Strength and Structural Load Path : Yes Embedment Steel and Pads Adequately Installed : Yes Reduction Factor input for Anchor # 5 j
Adequately Installed : Yes Embedment Length : (27.25 in. Min Reqd. to achieve full capacity) := 9.50 in.
Gap at Threaded Anchor : 0.00 in.
Edge Distance Edae 1 : 4.38 in.
Crack Size : 0.000 in. - Cracks traverses thru installation Essential Relays in Cabinet : No
- Adequate Equipment Base Strength and Structural Load Path : Yes Embedment Steel and Pads Adequately installed : Yes Reduction Factor input for Anchor # 6 Adequately Installed : Yes Embedment Length : (27.25 in. Min Reqd. to achieve full capacity) := 9.50 in.
Gap at Threaded Anchor : 0.00 in.
Edge Distance - Edge 1 : 4.38 in.
Crack Size : 0.000 in.
Cracks traverses thru installation
1 l
Northom States Power Company. Prairw Island Nuc6eer Generseng Plant GIP Rev 2 Corrected,2/14/92 SCREENING EVALUATION WORK SHEET (SEWS)
Status: No i
Sheet 11 of 13 ID : 81 ( Rev. 0 )
l Class : 20. Instrumentation and Control Panels and Cabinets Desenption : CONTROL PANEL B 1
{
Building : AUX l Floor El. : 735.00 l Room, Row / Col: Contml Room Manufacturer, Model. Etc. -
Essential Relays in Cabinet: No Adequate Equipment Base Strength and Structural Load Path : Yes Embedmont Steel and Pads Adequately Installed : Yes Reduction Factor input for Anchor # 7 I
l Adequately Installed : Yes Embedmont Length : (27.25 in. Min Reqd. to achieve full capacity) := 9.50 in.
Gap at Threaded Anchor : 0.00 in.
Edge Distance. Edge 1 : 4.38 in.
Crack Size : 0.000 in.
Cracks traverses thru Installation Essential Relays in Cabinet: No Adequate Equipment Base Strength and Structural Load Path : Yes Embedmont Steel and Pads Adequately installed : Yes Reduction Factor input for Anchor # 8 Adequately Installed : Yes Embedment Length : (27.25 in. Min Reqd. to achieve full capacity) := 9.50 in.
Gap at Threaded Anchor : 0.00 in.
Edge Distance. Edge 1 : 4.38 in.
Crack Size : 0.000 in.. Cracks traverses thru installation Essential Relays in Cabinet: No Adequate Equipment Base Strength and Structural Load Path : Yes Embedmont Steel and Pads Adequately Installed : Yes Reduction Factor input for Anchor # 9 Adequately Installed : Yes Embedment Length : (27.25 in. Min Reqd. to achieve full capacity) := 9.50 in.
Gap at Threaded Anchor : 0.00 in.
Edge Distance. Edge 1 : 4.38 in.
Crack Size : 0.000 in.
Cracks traverses thru installation Essential Relays in Cabinet: No Adequate Equipment Base Strength and Structural Load Path : Yes Embedment Steel and Pads Adequately Installed : Yes Reduction Factor input for Anchor # 10 Adequately Installed : Yes Embedmont length : (27.25 in. Min Reqd. to achieve full capacity) := 0.50 in.
Gap at Threaded Anchor : 0.00 in.
Edge Distance Edge 1 : 4.38 in.
- Crack Size : 0.000 in. Cracks traverses thru installation Essential Relays in Cabinet: No Adequate Equipment Base Strength and Structural Load Path : Yes Embedment Steel and Pads Adequately Installed : Yes
e Northom States Power Company. Pra6t$e island Nuclear Generating Plant GIP Rev 2, Corrected,2/14/92 SCREENING EVALUATION WONK SHEET (SEWS)
Status: No Sheet 12 of 13 10 : B.1 ( Rev. 0 )
l Class : 20. Instrumentation a.1d Control Panels and Cabinets Denenption : CONTROL PANEL B 1 Building : AUX l Floor El. : 735.00 l Room, Row / Col: Control Room Manufacturer. Model, Etc.
Redu-tion Factors Data Current : Yes Anc Paint Paltri No M
Van Vent RT RN RL RG RS RE RF RC RR RP RB RM 1
1 2663 70 N/A 1 00 1.00 0 43 1 00 1.00 1.00 0 93 1.00 1 00 1.00 1.00 1 00 3082 96 N/A 1 00 1 00 1 00 1 00 1 00 1 00 0 93 1.00 1.00 1.00 1.00 1.00 2
1 2663 70 N/A 1 00 1 00 0 43 1 00 1 00 1 00 0 93 1 00 1 00 1.00 1 00 1.00 3082 96 N/A 1 00 1 00 1 00 1.00 1 00 1.00 0 93 1.00 1 00 1 00 1.00 1.00 3
1 2663.70 N/A 1.00 1 00 0 43 1.00 1.00 1.00 0 93 1.00 1 00 1.00 1.00 1.00 3082 94 N/A 1 00 1 00 1 00 1 00 1 00 1.00 0 93 1.00 1.00 1 00 1.00 1.00 4
1 2663 70 N/A 1 00 1 00 0 43 1.00 1 00 1 00 0 93 1.00 1 00 1.00 1.00 1 00 3082 98 N/A 1 00 1.00 1.00 1.00 1 00 1 00 0 93 1 00 1.00 1.00 1.00 1.00 1
2663.70 N/A 1 00 1 00 0 43 1 00 1.00 1.00 0 93 1.00 1 00 1.00 1.00 1.00 306J 98 N/A 1 00 1 00 1 00 1.00 1.00 1.00 0 93 1.00 1,00 1.00 1 00 1 00
=
6 1
2663 70 N/A 1 00 1 00 0 43 1 00 1.00' 1.00 0 93 1 00 1 00 1 00 1 00 1.00 3082 98 N/A 1 00 1.00 1 00 1 00 1 00 1 00 0 93 1.00 1 00 1,00 1.00 1 00 7
1 2663 70, N/A 1 00 1 00 0 43 1 00 1.00 1 00 0 93 1 00 1.00 1 00 1.00 1.00 3082 96 N/A 1 00 1 00 1 00 1 00 1 00 1 00 0 93 1.00 1.00 1.00 1.00 1.00 8
1 2663 70 N/A 1 00 1.00 0 43 1 00 1 00 1 00 0 93 1.00 1.00 1 00 1.00 1.00 3082 98 N/A 1.00 1 00 1 00 1 00 1.00 1.00 0 93 1.00 1.00 1.00 1.00 1.00 9
1 2663 70 N/A 1 00 1.00 0 43 1 00 1.00 1 00 0 93 1.00 1 00 1 00 1 00 1.00 3082 98 N/A 1.00 1 00 1.00 1.00 1.00 1 00 0 93 1.00 1.00 1.00 1.00 1 00 10 1
2663 70 N/A 1.00 1 00 0 43 1 00 1.00 1 00 0 93 1 00 1.00 1 00 1.00 1.00 3082 98 N/A 1 00 1 00 1 00 1 00 1.00 1.00 0 93 1.00 1.00 1.00 1 00 1.00 Legend; N/A
= Not Applicable
- Pall
= Allowable Pull without Reduced inspection Vai8
= Allowable Shear without Reduced Inspection Palir
= Allowable Pull with Reduced inspection Vallr
= Allowable Shear with Reduced Inspection
= Outlier X
= Reduction Factor Not Used w
= Reduction Factor for Type of Anchorage RN
= Reduction Factor for installadon Adequacy RL
= Reduction Factor for Embedment RG
= Reduction Factor for Gap at Anchors RS
= Reduction Factor for Spacing RE
= Reduction Factor for Edge Distance RF
= Reduction Factor for Concrete Strength RC
= Reduction Factor for Concrete Cracks RR
= Reduction Fa-tor for Essential Relays RP
= Recluction Factor for Base Stiffness and Prying Action RB
= Reduction Factor for Base Strength and Load Path RM
= Reduction Factor for Embed. Sted and Pads Analysis Results ;
Analysis Performed : Yes
Northern States Power Company Pralrie Island Nuclear Generstmg Ptont GIP Rev 2, Corrected,2/14/92 o "
SCREENING EVALUATION WORK SHEET (SEWS)
Status: No Sheet 13 of 13 ID : B 1 ( Rev. 0 )
l Class : 20. Instrumentation and Control Panels and Cabinets Desenption : CONTROL PANEL B 1 Building : AUX 1 Floor El. : 735.00 l Room, Row / Col : Control Room Manufacturer, Model. Etc. :
Type of Analysis : Regular Spectral Accelerations (G's)
No N-S EW Verttcal Safety Factor 1
0.349 0.140 0.060 8.696 2
0 349 0.140
-0.060 9.755 3
0.349 0.140 0.060 8.696 4
0.349
-0.140
-0.060 9.755 5
0.349
-0.140 0.060 8 696 6
-0.349 0.140
-0060 9.755 7
0.349 0.140
-0.060 9.755 8
0.349
-0.140 0.060 8.696 9
0.140 0.349 0.000 7.209 10
-0.140
-0.349 0060 7.963 11 0 140
-0.349 0.060 7.209 12
-0.140 0.349
-0.060 7.963 13
-0.140 0.349 0.060 7.209 14 0.140
-0.349
-0.060 7.963 15 0.140 0.349
-0.060 7.963 16
-0.140
-0.349 0.063 7.209 17 0.140 0.140 0.150 14.416 18 0.140
-0.140
-0.150 25.313 19 0.140 0.140
-0.150 25.313 _
m 20
-0.140
-0.140 0.150 14.416 21
-0.140 0.140 0.150 14 416 22 0.140
-0.140
-0.150 25.313 23 0.140 0.140 0.150 14.416 24 0.140 0.140
-0.150 25.313 Minimum Safety Factor : 7.209 The anchorage can withstand 7.209 times greater seismic demand
Northom States Power Company. Preirte beland Nuclear Generating Plant GIP Rev 2, Corrected,2/14/92 SCREENING EVALUATION WORK SHEET (SEWS)
Status: Yes 1
Sheet 1 of 2 10 : 135-021 (Rev. 0) l Class : 21 - Tanks and Heat Exchangers Desenption : 11 RCP SEAL WATER RETURN HEAT EXCHANGER Budding : AUX l Floor El. : 715.00 l Room, Row / Col: K.3/8.0 i
Manufacturer. Model. Etc. :
BASIS : External analysis
- 1. The buckling capacity of the shell of a large, flat-bottom, vertical tank is equal to or greater N/A than the demand.
- 2. The capacity of the anchor bolts and their embedments is equal to or greater than the Yes demand.
- 3. The capacity of connections between the anchor bolts and the tank shell is equal to or Yes greater than the demand.
- 4. Attached piping has adequate flexibility to accommodate the motion of a large, flat-bottom, Yes vertical tank.
- 5. A nng-type foundation is not used to support a large, flat bottom, vertical tank.
N/A IS1QUIEMENI_REISMICALLY ADEQUAIE?
Yes CDMMENIA SRT: F. Stille(S&A) and G. Gore (NSP) 4/21/95 REF: Atlas Dwg D-2092-3,(XH 1001 14), Pioneer Dwgs NF 383131HH, NF 38299 27F, NF 38299 2, Tech.
Manual XH 1 1783 The vertical heat exchanger (126" high) is mounted on a 15" high Pedestal and is anchored with 1 3/8" J. Bolts.
The HX's seismic capacity was evaluated by calculation 93C2807-C-005. The cabulation shows that the HX has adequate seismic capacity.
There are no spatial Interaction issues.
Evaluated by:
Date:
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Attachment:
Pictures
l Northern States Power Company. Patrie Island Nuclear Generating Plant GIP Rev 2, Corrected,2/14/92 SCREENING EVALUATION WORK SHEET (SEWS)
Status: Yes Sheet 2 of 2 ID : 135-021 (Rev. 0) l Class : 21. Tanks and Heat Exchangers Desenption : 11 RCP SEAL WATER RETURN HEAT EXCHANGER Building : AUX l Floor El. : 715 00 l Room, Row / Col: K 3/8.0 i
l Manufacturer, Model, Etc.
E1CIURES 1
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Fig.1: RCP Seal Water Retum HX (135-021) Support Fig 2: Seal Water Return HX (135-021)
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Nenhem steens Power company. Prowse leaend Nuclear Genereens Plant GIP Rev 2, Corrected,2/14/92 SCREENING EVALUATION WORK SHEET (SEWS)
Status: Yes Sheet 1 of 2 10 : 163 021 (Rev. 0) l Class : 21. Tanks and Heat Exchangers Desenpton : 11 VOLUME CONTROL TANK Building : AUX l Floor El. : 715.00 l Room. Row / Col: H.72.9 Manufacturer. Model. Etc. :
BASIS : Extemal analyons 1 The buckling capacity of the shell of a large, flat bottom, vertical tank is equal to or greater N/A than the demand.
- 2. The capacity of the anchor bolts and their embedmonts is equal to or greater than the Yes demand.
- 3. The capacity of connectons between the anchor bolts and the tank shell is equal to or Yes greater than the demand.
- 4. Attached piping has adequate flexibility to accommodate the moton of a large, flat-bottom.
Yes vertical tank.
- 5. A nng type foundston is not used to support a large, flat-bottom, verticallink.
N/A 18 RQUIPMENT SEISMICALLY ADEQUATE 7 Yes CotillENIS SRTs are Djordjevic and Ridder 5/25/94 REF: Westinghouse Drawing 685J503,(NSP Dwg. XH 1-65) shts,1,2 ; Pioneer Drawings: NF 3830918 NF.
38309-2B, NF 38313-1HM, NF.38200-C.
This is an elevated tank mounted on 4 SWF31 legs. Each leg anchored to the reinforced cor. crete floor by 2 1" cast in place anchors. Tank and anchorage evaluation was done dy attemate calculations (93C2807 C-004) and included an evaluation of any potenital spatialinteractions of the attached level monitoring pipe which has only a 1" clearance to wall. This check was done at the top of the tank and it was determined that the piping will not impact the wall. There are no other seismic interaction issues. This calculation also demonstrated that the anchorage and load path capacity exceed demand, The tank weight used in the analysis was 17320 lbs Also the evaluation opf the applied piping nozzle loads was done in the referenced calculation.
Evaluated by:
Date:
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Attachment:
Pictures 9
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Northern St:t:s Power Comp:ni. Prcirts 13tand Nucicer G:ner; ting Pl:nt GIP Rev 2, Corrected,2/14/92 j
SCREENING EVALUATION WORK SHEET (SEWS)
Status: Yes Sheet 2 of 2 10 : 153-021 (Rev. 0) l Class : 21 Tanks and Heat Exchangers i
Desenption : 11 VOLUME CONTROL TANK Building : AUX l Floor El. : 715.00 l Room. Row / Col: H 7/6.9 Manufacturer Model, Etc.
i ElcTURES 1
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I Volume Control Tank (153-021) Leg Anchorage Detail l
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Northom States Power Company. Pro 6tte island Nuclear Generoting Plant GIP Rev 2, Corrected,2/14/92 SCREENING EVALUATION WORK SHEET (SEWS)
Status: Yes Sheet 1 of 1 10 : 253-021 (Rev. 0) l Class : 21. Tanks and Hoc. Exchangers Desenpton : 21 VOLUME CONTROL TANK Building : AUX l Floor El. : 715.00 l Room. Row / Col : H.7/11.1/
Manufacturer, Model. Etc. -
BASIS : External anahsis
- 1. The buckling capacity of the shell of a large, flat-bottom, vertical tank is equal to or greater N/A than the demand.
- 2. The capacity of the anchor bolts and their embedments is equal to or greater than the Yes demand.
- 3. The capacity of connections between the anchor bolts and the tank shell is equal to or Yes greater than the demand.
- 4. Attached piping has adequate flexibility to accommodate the motion of a large, flat bottom.
Yes vertical tank.
TA ring type foundation is not used to support a large, flat-bottom. vertical tank.
N/A 181QU12MENLSE18MICALLY. ADEQUATE 7 Yet COMMENIS SRT: F. Stille (S&A) and G. Gore (NSP) 5/30/95.
REF: Westinghouse Drawing 685J503, (NSP Dwgs. XH 165) shts.1,2; Pioneer Drawings NF 38309 38 and -4A, NF-383131HH, NF 38200-C.
Elevated tank mounted on 4 SWF31 legs. Each leg anchored to reinforced concrete floor by 2 1" cast-in-place anchors. There are no potential seismic interactions observed. This tank, the anchorage and the seismic input for this component is identical to that for component ID# 153-021. The actual tank evaluation analysis was done in calculation 93C2807-C-004. This calculation demonstrated that the anchorage and load path capacity exceeded demand. The tank weight used in the analysis was 17320 lbs. The calculation also evaluated the applied piping nozzle loads.
^
Evaluatec by:
Dato:
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NortNm States Power Company. Proerte loland hc6eer Generseng Plant GIP Rev 2, Corrected 2/14/92 OUTLIER SE13MIC VERIFICATION SHEET (OSVS)
Sheet 1 of 1 i
10 : 053-251 (Rev. 0) l Class : 21. Tanks and Heat Exchangers Desenpton : 121 COOLINO WATER PUMP DIESEL OIL S10 RAGE TANK Buil$ng : SSCRN l Floor El. : 695.00 l Room. Row / Col: C1/51.5
- 1. OUTLIER ISSUE DEFINITION Tanks and Haat Exchangers
- a. Identify all the screening guidelines which are not met. (Check more than one if several guidelines could not be satisfied.)
Shell Buckling Anchor Botts and Embedmont Anchorage Connections Flexibility of Attached Piping X
Other
- b. Describe all the reasons for the outfier (I e., if all thJ listed outlier issues were resolved, then the signatories would consider this item of equipment to be verified for seismic adequacy).
The tanks are an outilers because the necessary fuel buried piping between the tanks and the screenhouse must be demonstrated to be able to withstand the potential seismic differential anchor motions which could occur during an earthquake event.
2ELOP_ DIED _MEIliOD_OF OUTLIER RESOLUTION fOsthtlal)
- a. Defined proposed method (s) for resolving outlier.
Detailed analysis of the buried piping including sufficient soll structure interaction analysis for the screenhouse and tfie tank slab to accurately determine the potential seismic anchor motloris between these two structures, b, Provide information needed to implement proposed method (s) for resolving outlier (e.g., estimate of fundamental frequency).
4 L_ CERTIFICATION:
The it; formation on this OSVS is, to the best of our knowledge and belief, correct and accurate, and resolution of the outlier issues listed on the previous page will satisfy the requirements for this item of equipment to be verified for seismic adequacy:
/
gg Approved by:
Date:
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- e Northem States Power Company. Praine island Nuc. lear Genersung Plant GIP Rev 2. Corrected,2/14/92 SCREENING EVALUATION WORK SHEET (SEWS)
Status: No Sheet i of 1 ID : 053 251 (Rev. 0) l Class : 21 Tanks and Heat Exchangers Desenption : 121 COOLING WATER PUMP DIESEL OIL STORAGE TANK Building : SSCRN l Floor El. : 695 00 l Room. Row / Col : C1/51.5 Manufacturer. Model, Etc.
BASIS : External analysis
- 1. The buckling capacity of the shell of a large, flat-bottom, verttCal tank is equal to or greater N/A than the demand.
- 2. The capacity of the anchor bolts and their embedments is equal to or greater than the Yes demand.
- 3. The capacity of connections between the anchor bolts and the tank shellis equal to or Yes greater than the demand.
- 4. Attached piping has adequate flexibility to accommodate the motion of a large, flat bottom, No vertical tank.
5 A ring type foundation is not used to support a large, flat-bottom, vertical tank.
N/A IS_EQU1EMENI_SElSMCALLYADEQUATE7 No COMMENIS SRT: Djordjevic cnd Ridder-5/17/94 REF: Pioneer Drawings NF 39287 SM, NF 392601, NF 38229, NationalValve Dwg # A-6720, A-6722, A-67??,
Morehead Dwg # D-69070*
The cooling water diesel oil storage tank is buried in a vault (pit) covered by a manhole cover cannot fall in the pit.
Per the referenced dwgs the tank is mounted on a concrete slab which is 1' thick and is anchored to the slab by 5 holdown straps which surround the tank and are then embedded into the concrete. In addition lean concrete wedges are poured in place at the base of the tank and then the entire tank is buried with backfill up to about the tank centerline and then gravel appears to place from that point to grade Therefore the tank is judged to have cdequete seismic capacity. The tank slabs are independent and are not tied into the screenhouse foundation.
There is signJicant buried piping between the tanks and the screenhouse building which provides fuel oil to the screenhouse cooling water diesal pumps. Because the tanks are on a seperate slab from the bulleg this buried piping could be subjected to significant differential displacemental motion during an earthquake event and this type of large differential motion is a known earthquake failure mode for buried piping. Therefore tanks are an cutliers because the necessary fuel piping must be demonstrated to be able to withstand the potential seismic differential anchor motions which could occur during an earthquake event.
Evaluated by:
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l Northern States Power Company. Preer6e loland Nuclear Generat6ng Plant GIP Rev 2, Corrected 2/14/92 5
l OUTLIER SElSMIC VERIFICATION SHEET (OSVS)
Sheet 1 of 1 i
ID : 153-011 (Rev. 0) l Class : 21. Tanks and Heat Exchangers Desenption : 11 PRESSUMZER RELIEF TANK Building : CNTMT l Floor El. : 695.00 l Room, Row / Col: 15/95 LQUTLIEM ISSUE DEFINITION Tanks andReat Exchangers
- a. Identify all the screening guidelines which are not met. (Check more than one if several guidelines could not be satisfied.)
Shell Buckling Anchor Botts and Embedmont Anchorage Connections X
Flexibility of Attached Piping Other
- b. Describe all the reasons for the outlier (i.e., if a!! the listed outfier issues were resolved, then the signatories would consider this item of equipment to be verified for seismic adequacy).
The Tank has two gusset support plates and both plates have Slotted lloles in the axial direction.
2.fEQEQ3EDREIHQD OF OUTLIERRESOLUTION lOptional)
- a. Defined proposed method (s) for resolving outlier.
(1) A Plato could be welded to over the holes on one of the support plates to eliminate the axial support
- gaps,
- b. Provide information needed to implement proposed method (s) for resolving outlier (e.g., estimate of fundamental frequency).
L.CERIlEICAll0M The information on this OSVS is, to the best of our knowledge and belief, correct and accurate, and resolution of the outlier issues listed on the previous page will satisfy the requirements for this item of equipment to be verified for seismic adequacy:
ll U1 A)'-
Approved by:
Date'
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Northem Statee Power Company Preitte leland Nuc6eer Genersong Plant GIP Rev 2, Corrected,2/14/92 SCREENING EVALUATION WORK SHEET (SEWS)
Status: No Sheet i of 7 ID : 153-011 (Rev 0) l Class : 21. Tanks and Heat Exchangers Desenption : 11 PRESSURIZER RELIEF TANK Building : CNTMT l Floor El. : 695.00 l Roem, Row / Col: 15/95 Manufacturer, Model, Etc. :
BASIS : Horizontal TANK analysis 1, The buckling capacity of the shell of a large, flat-bottom, vertical tank is equal to or greater N/A than the demand.
- 2. The capacity of the anchor bolts and their embedments is equal to or greater than the Yes demand.
- 3. The capac:'y of connections between the anchor bolts end the tank shell is equal to or No greater than he demand.
- 4. Attached piping i'as adequate flexibikty to accommodate the motion of a large, flat bottom, Yes vertical tank.
- 5. A nng type foundation is not used to support a large, flat-bottom, vertical tank.
N/A (S.EQUIPMENLSEjSMICALLY ADEQUATE 7 NQ CONIWlENTS SRTs are Djordjevic and Ridder 5/24/94 REF: Tank Drawings: W 685J487 (XH 1 127); Anchorage: Pioneer Dwg# NF 38405P Horizontal tank mounted n 2 saddles with 3 gussets on each side of a center plah Per the Referenced Pioneer drawings each saddle is anchored by 4 - 1" 90 degeree J Bolt anchors 2 or'. either side of center plate. Unit Embedment length was 33". Tank Materials, Dimensions, etc. were taken from the referenced Westinghouse Drawing.
An initial Analysis was done using the GIP Horizontial Tank evaluation methodology but the Tank didn't meet two cavaets for application of this evaluation approach:
(a) Both Base Plates were slutted (b) Tank Density was > 75 lbf/ft^3 For item (b) the calculated tank density was based on the assumption that the tank was completely flooded and was determined as: (62960 lbs/800 fla3) = 78.7 lbs/ft*3 which exceeds the GlP Guideline by only 4%. In the general operation of the plant this tank is more a convience then a requirement in that it is used to contain normal operating discharges form the Pressurizier PORVs and Code SRVs It is equiped with a rupture disk should prolonged valve operation fill the tank. Therefore the assumption of a completely flooded tank is very conservative.
Therefore since this is a conservative assumption and the the value is only 4% above the the GIP maximuin the tank analysis was run with a value of tank density of 74.99 lbs/ft*3.
For item (a) the Tank will evaluated as if one set of gaps were zero to determine the anchorage :apact ' M develop suggested fixes for the Outlier resolution sheet.
The Tank Analysis showed a frequency of 22.6 hz and therfore used the peak g's for evaluation of the anchorage which showed that capacity was less than demand. The frequency of 22.6 hz is sigaificantly above the spectral
Northom States Poww Company. Pro 6th le6end Nuclear Genereung Mont GIP Rev 2, Corrected,2/14/92 SCREENING EVALUATION WORK SHEET (SEWS)
Status: No Sheet 2 of 7 10 : 153-011 (Rev. 0) l Class : 21. Tanks and Heat Exchangers Desenpeon : 11 PRESSURIZER REUEF TANK Budding : CNTMT l Floor El. : 695.00 l Room. Row / Col: 15/95 Manufacturer, Model, Etc. :
peaks anf therefore by reviewing the spectral curves a g level of.22g can be used for the tank evaluation. With this g level the anchorage margin is.494g/.22g = 2.29 therfore capacity exceeds demand. Hand Calculations (93C2807-C 012) were done to determine the Tank anaYsis input parameters and evaluate the support load path and the applied piping noule loads.
The tank is an outlier due to the slotting of holes in both support plates and an OSV3 was generated.
Evaluated by:
/
Date:
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TANK Analysis Results a
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l Northern States Power Company. Prairie island Nucl:ar Genorcting Plant GIP Rev 2, Corrected,2/14/92
{
SCREENING EVALUATION WORK SHEET (SEWS)
Status: No Sheet 3 of 7 ID : 153-011 (Rev. 0) l Class : 21. Tanks and Heat Exchangers
)
Desenption : 11 PRESSURIZER REllEF TANK Butiding : CNT MT l Floor El. : 695.00 l Room. Row / Col: 15/95 Manufacturer, Model. Etc.
)
PICTURES i
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s Fig.1: Pressurtzier Relief Tank (153 011) Axial View Fig 2: Pressurizier Releif Tank (153-011) Anchorage and Support Saddle Detal a
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Northom States Power Company. Prair6e loland Nuclear Generat6ng Plant GIP Rev 2 Corrected,2/14/92 SCREENING EVALUATION WORK SHEET (SEWS)
Status: No Sheet 4 of 7 ID : 153-011 (Rev. 0) l Class : 21 - Tanks and Heat Exchangers Desenption : 11 PRESSURIZER RELIEF TANK Building : CNTMT l Floor E!. : 695.00 l Room. Row / Col: 15/95 Manufacturer, Model. Etc. -
TANK Analysis Results Step 1 -Input Data a) Assumptions
- 1. Tank is cyhndncal, honzontally ownted and supported on saddles.
Yes
- 2. Tank and saddles are made of carbon steel.
Yes
- 3. Saddles are uniformly spaced.
Yes
- 4. Saddles overhang is less than spacing / 2.
Yes
- 5. Base plates have slotted anchor bolt holes for thermal growth except for the base plate under Yes 4
the fixed saddk
- 6. Imposed nozzle loads are not significant.
Yes
- 7. The tank four 7. con is adequate.
Yes
- 8. Anchor bolts are cast in place or expansion type.
Yes b) Materials Weight of Tank + Fluxl 62.92 kips Weight Density of Tank + Fluid 74.99 lbs/ft*3 Saddle Elastic Modulus 29000.0 ksi Saddle Shear Modulus 11500.0 ksi Base Plate Yield Strength 30.0 ksi Anchor Type 1 in 90 deg. J. Bolts c) Dimensions Tank Diameter, D 8.0 ft Tank Length. L 17.58 ft Tank Thickness, t 0.437 in Height of Tank + Fluid C.G., Hcg 5.38 ft Number of Saddles 2
Saddle Spacing S 9.33 ft Saddle Height, h 15,0 in Saddle Shear cross-sectional area 64.71 in^2 Saddle Weak Axis Moment of Intena 134.0 in^4 Number of Bolt Locations / Saddle 2
Number of Bolts / Botting Location 2
Extreme Bolt Spacing. D' 5.22 ft Anchor Bolt Eccentncity, e 2.25 in Weld Thickness 0.38 in Base Plate Thickness 0.625 in
- - - ~.
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Noethern States Power Company. Praerte loland Nuclear Genereeng Plant GIP Rev 2. Corrected,2/14/92 l
SCREENING EVALUATION WORK SHEET (SEWS)
Status: No Sheet 5 of 7 i
ID : 153-011 (Rev. 0) l Class : 21 - Tanks and Heat Exchangers Desenption : 11 PRESSURlZER RELIEF TANK Build'ng : CNTMT l Floor El. : 695.00 l Room. Row / Col : 15/95 Manufacturer. Model. Etc.
d) Anchor Bolts Type = 90 Deg J-Bolt Diameter = 1 in Manufacturer =
Product Name =
Pullout Shear Nominal Capacity 26 69 kips 13 35 kips l Concrete Compression Strength, fc' = 3000.0 psi l
Reduction Parameters Capacity Reduction Factor Label Check Condition Pullout Shear
- 1. Type of Anchorage Yes 1.0 1.0
- 2. Installation Adecuacy Yes installation is adequate 1.0 1.0
- 3. Embedment Length Yes Embedment Length = 42.0 0.8 1.0 in
- 4. Gap at Threaded Anchors Yes Gap stze = 0.0 in 1.0 1.0
- 5. Spacing between Anchorages Yes 1.0 1.0
- 6. Edge Distance Yes Edge Distance = 8.75 in 1.0 1.0
- 7. Concrete Strength and Condition Yes 0.93 0.93
- 8. Concrete Crack Location and Size Yes Crack Size = 0.0 in 1.0 1.0
- 9. Essential Relays in Cagnets Yes Essential relays are lot 1.0 1.0 present
- 10. Base Stiffness and Prying Action Yes 1.0 1.0
- 11. Equipment Base Strength and Yes Base strength ar d load path 1.0
' 1.0 Structural Load Path are O.K.
- 12. Embedmont Steel and Pads
" ~Yes Installation is not apoi> cable 1.0 1.0 Does the tank satisfy all the assumptions and is within the applicable range of parameters?
Y13 Step 2 - The allowable bolt loads Allowable Tension Load. Pu' 19.768 kips Allowable Shear Load, Vu' 12.36 kips Step 3 - Determine base plate bending strength reduction factor lRB l
0.1976 l
Northern States Power Company. Proene loland Nuclear Gewstmg Plant GIP Rev 2, Corrected,2/14/92 SCREENING EVALUATION WORK SHEET (SEWS)
Status: No Sheet 6 of 7 10 : 153-011 (Rev. 0) l Class : 21 - Tanks and Heat Exchangers Desenption : 11 PRESSURIZER RELIEF TANK Building : CNTMT l Floor El. : 695.00 l Room Row / Col: 15/95 Manufacturer, Model. Etc. -
Step 4 - Determine base plate weld strength reduction factor lRW l
1.8717 l
Step G - Determine the anchorage tension and shear allowable loads
~
licwable Anchorage Tenslon Load, Pu 3.906 kips Allowable Anchorage Shear Load, Vu 12.36 kips Step 6 - Calculate the ratios and values alpha (Pu/Vu) 0.32 Wb 7.87 kips / bolt Vu / Wb 1.57 Heg / D' 1.031 Heg / S 0.577 F1 2.236
~
F2 2.454 Step 7 - Determine the acceleration capacity of the tank anchorage lamoda_1 0.703 G lambda _u 0.494 G Anchor Acceleration capacity, lambda 0.494 G Step 8 - Determine the maximum saddle spacing for transverse and vertical rigid frequency response l Maximum Saddle Spacing, Sc l
21.07 ft l
Step 9 - Compute the resonant frequency of the tank in the longitudinal direction Saddle Stiffness, Ks 3229.373 kips /in Resonant Frequency of Tank in Longitudinal Direction 22.4 Hz y
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l Northom States Power Company. Pfeifte letand Nucteer Generating Plant GIP Rev 27 Corrected,2/14/92
~
-8 SCREENING EVALUATION WORK SHEET (SEWS)
Status: No Sheet 7 of 7 IC : 153-011 (Rev. 0) l Class : 21 Tanks and Heat Exchangers Desenpton : 11 PRESSURIZER RELIEF TANK Building : CNTMT l Floor El. : 695.00 l Room. Row / Col: 15/95 Manufacturer, Model, Etc. -
Step 10 - Determine the solemic demand acceleration l Peak Spectral Acceleraton, SPA (g) l 1.589 /4.0% damping /
l Tank is flexible in one of the three directions (transverse, vertical or, longitudnal).
Tank is an outlier because anchorage acceleration capacity is less than SPA Step 11 - Check the saddle stresses The program does not check the saddle stresses Check the saddle stresses by an independent calculation RWitiftlary 18 EQUlPMENT SEISMICALLY. ADEQUATE?.
No The tank is an outlier becapse of -
- anchorage acceleration capacity is less than SPA
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