ML19308A982
| ML19308A982 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 05/26/1977 |
| From: | Parker W DUKE POWER CO. |
| To: | Case E, Schwencer A Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7912120745 | |
| Download: ML19308A982 (24) | |
Text
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[O "" 1(f.s 9 17 708 NiiC DISTRinUTION Fon PsulT 50 DOCKET MATERIAL TO:
FROM:
DATC of 00 Cut.tt tJT Duke Power Company 5/26/77 Mr. A. Schwencer Charlotte, North Carolina x
William O. Parker, Jr.
ox7c nIf5'lM ULETTER O NOToRIZ E O PROP INPUT Fonu.
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S 1G,A) F B DESC4* TION ENCLOSURE a
Consists of requested additional information
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concerning the Unit No. 1 Inservice
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Inspection Requirements.......
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Mr. Edson G. Case, Acting Director 4
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Office of Nuclear Reactor Regulation 1
U. S. Nuclear Regulatory Commission
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Washington, D. C.
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pl i-4 g Attention:
Mr. A. Schwencer, Chief L
Operating Reactors Branch #1 4'"
Reference:
Oconee Unit 1
- Docket No. 50-269
Dear Sir:
In response to your April 5, 1977 letcer which requested additional information concerning the Oconee Unit 1 Inservice Inspection Require-ments, the attached information is provided to supplement our October 1, 1976 submittal.
Very/ truly yours,,,
/
d uL. E d./ >
N William O. Parker, Jr '
MST:ge Attachment r
771530128
l RESP 03Si 0 REQUEST FOR ADDITIONAL INFORL..iION CONCERNING THE OCONEE 1 INSERVICE INSPECTION PROGRAM
' ATTACHMENT 1 "Conformance with ASME Section XI, Inservice Examination" Comments QUESTION 1.
Provide additional information using the letter from A. Schwer.cer, Chief, ORB #1 to W. O. Parker, Jr., Vice President, Steam Production Duke Power Company, dated November 30, 1976, as guidanca, to justify the request for relief from the inservice examination requirements specified in the 1974 edition of the Section XI Code through the summer 1975 addenda for Code Class 1, 2 and 3 components.
RESPONSE: to our October 1,1976 submittal described those, general exceptions which are taken to the ASME Section XI Code due to anticipated impracticalities which was felt would arise during examination of certnin Duke Class B and C components. Any portion for which it is determined that relief from the code requirements is necessary will be submitted to the NRC in accordance with Appendix B of Mr. A. Schwencer's letter to Mr. W. O. Parker dated November 30, 1976. At this time, the only compo-nent for which specific relief is requested is the examination of the reactor vessel nozzles. This request for relief is as follows:
1.
Component for which relief is requested:
a.
Name and Number: _ Reactor Pressure Vessel; NRC Docket No. 50-269 b.
Function: Reactor Core Support, Reactor Coolant Pressure Boundary c.
ASME Section III Code Class: Equivalent Class I per NRC Regulatory Guide 1.26, Revision 2 d.
Valve Category: Not Applicable 2.
ASME Section XI requirement that has been determined to be impractical:
ASME Boiler and Pressure Vessel Code Section XI,1974 Edition through Summer 1975 Addenda. Paragraph IWB-2411; Subarticle IWB-2500; Table IWB-2500 Category B-D; Table IWB-2600 Ites No. Bl.4.
3.
Basis for Requesting Relief:
The net effect of the above Code requirements is that four nozzles, of a total of eight, must be examined by the end of 80 months of commer-cial operation. Due to core support structures design of Oconee 1, only the two reactor coolant outlet nozzles are accessible without removing the core barrel, which in turn requires complete defueling.
This requirement is, therefore, considered to be impractical.
- 4. and 5.
Alternate Examination and Implementation Schedule.
The following examination program is proposed in lieu of the Code require-ments.
Examination Schedule (Elapsed Time Since Commercial Components to be Examined Service Date) l Reactor Coolant Outlet Nozzle Approximately 40 months 1 1
1 Reactor Coolant Outlet Nozzle Approximately 80 months 4 Reactor Coolant Inlet Nozzles Approximately 120 months 2 Core Flooding Nozzles Approximately 120 months 1Different nozzle will be examined each inspection This program reflects the Reactor Vessel Nozzle examination previously contained in the Oconee Technical Specifications.
l QUESTION i
2.
Clarify whether the required inservice examination will be witnessed i
or verified by a third party inspector even though South Carolina is not an ASME Code state.
RESPONSE
The required inservice examinations will not be witnessed by a third party inspec to r.
I 1
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i ATTACmfENT 2 "Conformance with ASME Section XI, Subsection IWP, Pump Testing" Comments QUESTION I
1.
In order to evaluate the Oconee 1 pump testing program the following information is requested:
a) A list identifying each pump to be tested by system and applica-tion.
b) The test parameters that will be measured for each pump.
c) The test intervals, i.e., monthly during operation or only during cold shutdown.
RESPONSE
The October 1, 1976 submittal provided a listing of safety-related pumps which are considered to be ASME Class 1, 2 or 3 and which are provided on emergency power source. These pumps are to be tested in accordance with IWP to the extent practicable, consistent with the existing design. The attached table provides the listing of pumps to be tested by system and application. The test parameters and test intervals for these pumps are j
also indicated.
QUESTION 2.
When certain parameters are not going to be tested and relief is requested, provide the following information:
a) Specifically identify the ASME Code requirement that has been determined to be impractical for the pu=p.
b) Provide-information to support the determination that the require-ment in (a) is impractical.
1 c) Specify the inservice testing that will be performed in lieu of i
the ASME Code Section XI requirements that have been determined to be-impractical or provide the basis for operation of this pump without this ISI.
d) Provide the schedule for implementation of the procedure (s) in (c) above.
RESPONSE
The following relief from the requirements of ASME,Section XI, Subsection IWP is requested:
1.
a) Requirement:
IWP-3300, IWP-3400 (a) Monthly testing of low pres-sure injection system pump 1A during normal ~ operation.
d b) Reason: During normal plant operation, the LPI pumps can be tested only in the recirculation mode to the BWST. 'The "A" pump
,v.
B
-4_
can only be tested using a piping line-up which contains a 3 inch section of pipe. This restricts flow tu approximately 1150 to 1550 gpm. At this low flow, the installed flow and diff erential pressure instrumentation does not have sufficient accuracy and the relatively flat pump head curve combines to prevent repeata-bility of this test.
c) Proposed Testing: During cold shutdowns (or monthly in the event of frequent shutdowns) the "A" pump can be fully tested in Decay Heat R moval model. During normal plant operation, the pump will be operated in recirculation mode conthly for 15 minutes or until vibration readings are taken, whichevery is longer. Since this pump is used primarily during cold shutdown operation, degradation is not expected during periods of power operation.
d) This schedule for testing has been implemented.
2.
a) Requirement:
IWP-3300 (Table IUP-3100-1) Flow Measurement. For Low Pressure Service Water (LPSW) pump "C".
b) Reason: The LPSW pumps supply two headers, LPA and LPB. The LPB header contains only E.S. components which are equipped with flow transmitters. LPA supplies both ES components and a subheader which supplies Non-ES auxiliary equipment which can be isolated only if both Units 1 and 2 are at cold shutdown. The output of pumps A & B may be measured by isolating the two headers so that the entire output of the pump being tested goes into "B" header while "C" pump supplies "A" header. However, "C" pump cannot be isolated from "A" header while operating.
c) Proposed Testing: All other parameters will be tested on "C" pump. The ability of "C" pump to supply the normal requirements of "A" header (which is approximately the same as the ES flow) will verify the general performance of the pump.
d) This testing procedure has been implemented.
3.
a) Requirement:
IWP-3300 (Table IWP-3100-1) Suction pressure measure-ment for Spent Fuel Pool Cooling, concentrated Boric Acid, and Low Pressure Horic Acid pump, b)
It is _not considered practical to perform these suction pressure measurements since the necessary instrumentation does not exist.
c) Proposed Testing: Level indications exist for the pool / tanks which supply these pumps. These levels, along with known static head differences from reference levels to pump suctions will pro-vide an approximate indication of the pump suction pressure.
Velocity losses should be relatively constant from test to test due to the repeatability of flow rates and valve positions for the test.
d) This test procedure has been implemented.
4.
a) Requirement:
IWP-3300 (Table IWP-3100-1) Flow for Concentrated Boric Acid and Low Pressure Boric Acid Pumps.
b) Reason:
It is not practical to perforu these measurements since flow measurement devices do not exist ic. these lines, c) Proposed Testing: None possible for this parameter.
. 5.
a) Requirement:
IWP-3300 (Table IWP-3100-1 footnote 2), Inlet Pressure Pi, for all pumps which are in operation on a routine basis at the time the test is started.
b) Reason: Several systems are normally in operation with one or more pumps running. Taking inlet pressure prior to pump startup would require an additional transfer to another pump. This (1) increases the time required for the test, (2) causes additional wear on the pumps due to extra starts, (3) on some systems this will require additional radiation dose during valve lineups prior to swap-over, and (4) presents additional opportunity for hu=an error during transfers.
c) Proposed Testing:
Inlet pressure will be taken prior to startup of any standby pumps.
Since in most systems standby and operating pumps are alternated periodically, all pumps will be checked periodically. Also, on systems where the inlet piping is common, the operational pump will affect the inlet pressure of the standby pump so that operating pressure on one pump would be the same as pre-start pressure on the standby pump.
d). This testing procedure has been implemented.
6.
a) Requirement:
IWP-3300 (Table IUP-3100-1), Lube Oil Level for EPI, CBAT and LP Boric Acid Pumps.
b) Reason': No indication exists to verify lube oil level without partial disassembly of the pump.
c) Proposed Testing: None on this parameter.
7.
a) Requirement:
IWP-3210, (Table IWP-3200-2) Allowable Ranges of Test Quantities.
b) Reason:
In reviewing Section IWP-4100, a general discrepancy was noticed. This is that IWP-4111 and Table IWP-4110-1 specify that an instrument full scale range may be four times the reference value with nominal errors (in most cases) of i 2% of full scale.
This permits an arror range of i 8% of the reference value. By Table IUP-3100-2, flow and pressure readings are allowed to range only +2,
-6% (flow) and +2, -7% (pressure). Therefore, a test could fail (exceeding the +3% required to enter the Required Action Range) entirely due to instrument error. Even recalibra-tion per IWP-3230(b) would not help if the instrument was still within its i 2% full scale accuracy.
c) Proposed Testing: Therefore, it is requested that per IWP-3210 the ranges en flow and pressure be extended as shown:
l Alert Ranges Required Action Range Test Quantity Acceptable Range Low Values High Values Low Values High Values AP
.92 to 1.08aPr
.90.to.92aPr 1.08 to 1.10aPr
<.90 Pr
>1.10aPr Q
.92 to 1.08 Qr
.90 to.92 Qr 1.08 to 1.10 Qr
<.90 Qr
>l.10 Qr Also, it is requested that relief from Table IWP-4110-1 be granted for the installed plant instrumentation listed below which have nominal tolerances greater than i 2% of full scale:
Instrument IWP IWP Existing Number Pump Parameter Tolerance Ft-75 HPI Pumps Flow i 2.5%
Ft-2A R.B. Spray Flow *
+ 3%
Ft-3A R.B. Spray Flow i 3%
Lt-1 Spent Fuel Level for suc-i 2.7%
Cooling clon pressure Pt-17Fgr. s CBAT Pump Disch. Press.
i 1.6% with span greater than 4 times the reference value i
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Item High Pressure Injection Pumps Mo HS X
X X.
X 2
X X
(lA, 1B, IC) Primary Make-up 1
AP Low Pressure Injection Pumps 2
Decay Heat Removal MO NA X
X X
X X
X X
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lA, 1B, 1C Reactor Building Spray Pumps M0 HS X
X X
X X
X X
lA, 1B 1
AP Lcw Pressure Service Water M0 NA X
X 2
X X
X X
Pumps - 1A, 1B, lc Services Decay Heat Coolers Reactor Building Vent. Cool,ers Spent Fuel Pool Cooling Pumps MO NA 2
2 X
X X
X X
1A, 1B i
Emergency Feedwater Pump MO NA X
X X
X X
X X
Concent. Bor'c Acid Pu=p MO NA 2
2 2
X 2
X X
LWD-P22 Boric Acid Addition i
Low Pressure Boric Acid Pumps M0 NA 2
2 2
X 2
X X
1A, 13, Boric Acid Addition e
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4 Notes:
Therefore, per IWP-3400 (a), they will be tested within 7 days after any cold shutdown which coincides with the due date of the test.
- 2. See attached list of requested exemptions for exceptions.
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ATTACHMENT 3 "Conformance with ASFC Section XI, Subsection IWV, Valve Testing" Comments QUESTION 1.
Provide code class designations for all valves tested.
2.
On your table identify each valve in ASME Section XI Cat. A that will be leak tested during refueling outages.
3.
Provide the test intervals for all valves to be tested. For check valves, identify those that will be exercised only during cold shutdown.
RESPONSE
The October 1, 1976 submittal provided a listing of those safety-related ASME Class 1, 2 and 3 valves for which testing is considered to be required.
This listin3 was provided to meet the requirements of Section IWV-1400 which requires the owner to identify the specific valves to be tested.
Since no differentiation in testing requirements exist for various ASME class valves, the specific code class designation of each valve is unneces-sary.
Valves which are classified as ASME Section XI Category A valves are indica-ted on the table of valves provided in the October 1, 1976 submittal. All valves which require leak tests will be tested annually, most probably during the refueling outage.
Valves will be tested at the frequency required by ASME Section XI, Subsection IWV unless specifically identified on the valve table. Please note a corrected 3
copy of the valve list is attached.
]
With regard to check valves, the testing frequency will be at least quarterly unless indicated that it cannot be performed during power operation.
In these cases, pursuant to IWV-3520(b) these valves will be exercised during each plant cold shutdown but not more of ten than once every 9 months.
QUESTION 4.
Where relief has been requested from certain requirements of the code, specify the inservice testing that will be performed in lieu of the ASME Code Section XI requirements that are impractical or provide the bases for operation of this valve without this ISI. Also provide the schedule for -implementation of this testing.
RESPONSE
The valve listing attached identifies those valves for which certain requirements of the code are impractical.
Valves with a comment code."1" are to be tested at time other than power operation as is permitted by Subsections IWV-3410 and IWV-3520. Those valves with a comment code "2" are impractical to leak test due to the lack of appropriate test connections or isolation valves. Those valves with a'co= ment code "3" are impractical to exercise test.
No testing will be performed in lieu of the ASME Code Section XI requirements that are impractical.
. The intent of 10CFR50.55a is to require that throughout the service life of a nuclear facility the inservice inspection program shall meet the requirements of Section XI of editions of the ASME Boiler and Pressura Vessel Code and Addenda which become effective to the extent practical.
It is our understanding that the code does not require upgrading of the design of the facility, but rather where practical, to improve the inspec-tion or testing criteria or methods. In the case of Subsection IUV for valve testing, certain provisions of the code have been identified which are not practical to meet. These pri=arily are the results of insufficient test connections or isolation valves to enable leak tests to be performed; inappropriate piping configurations to permit exercise testing of check valves; or unaccessibility of components to verify operation of the valve to be tested. Continued operation without inservice inspection of these components is not considered to be detrimental to the public health and safety over the "as licensed plant" for the following reasons: Many of the valves are subjected to high system pressures during normal operation and unacmaptable leakage would be readily detected, e.g., core flood tank valves CF-3, CF-4, CF-19, CF-33, etc.
Some valves which cannot be tested perform containment isolation functions, however, the downstream piping is adequately designed for accident conditions, e.g., HP-20 reactor coolant
. pump seal return; many valves which cannot be specifically tested are but one of two redundant isolation valves. Additionally, all systems are functionally tested during the periodic containment integrated leak rate test to provide assurance of operability.
In consideration of the burden which would be imposed to enable testing of these components in accordance with the code, it is not felt that the health and safety of the public would be significantly improved.
t Additionally, the following specific relief from the code is requested:
1.
'a)
Requircment: IWV-3410(c) Power operated valves.
b) Reason: Power operated valves which operate in very short time periods (in the order of one second) are difficult to accurately time. In these instances, the specified limiting valve of the full stroke time will generally be considerably greater than the actual full stroke time. In accuracies in timing contribute to not being able to meet the acceptance criteria of IWV-3410(c)(3).
c) Proposed testing:
If any valve with a previously measured stroke time less than or equal to one second is observed to increase in stroke time to slower than 1.5 seconds, test frequency shall be increased to once each month until corrective action is taken, at which time the original test frequency shall be resemed. In any case, any abnormality or erratic action shall be reparted."
QUESTION 5.
Provide simplified piping diagrams of systems which must function to safely shutdown the ' plant or mitigate the consequences of an accident.
Active components on the above systems which must change position should be identified. Also, provide a narrative description of the valve line-ups required of the systems identified above each of their safety functions.
. RESPONSE:
P & ID draings have been supplied for review. These drawings indicate active components and should provf.de adequate information for personnel familiar with operation of a B&W steam supply system to perform this review, If assis-tance is required in understanding the operation of these systems, this could more readily be resolved in verbal discussions than in the requested narrative descriptions.
QUESTION 6.
In addition to the above comments, we have found that in some c-ses, valves important to plant safety were omitted.
Comments on these valves will*be made by drawing number.
a) Dwg PI-100-A Only 2 of the three pressurizer relief valves
. listed. Valve # 1RC-66 should be included.
b) Dwg PO-101A Valves listed on this drawing are containment isolation valves.
Check valve #RP-194 should be included if possible to the test program, c) Dwg PO-102A Valves BS-3 and BS-4, Power operated valves on the suction lines to the reactor building spray pumps are omitted. They should be included or justification provided for not including them.
d) Dwg PO-103A-1,2,3 - Ch(ck valves BS-14 and BS-19 are proposed to be tested every 5 vears. A source of instru=ent air exists (accord-ing to the drawin, for spray nozzle testing. The licensee should o
consider using the instrument air to test the check valves on a more frequent schedule.
e)
Dwg PO-122A Only one of sixteen main steam safety reliefs is listed. Provide justification for not including the others.
f)
Dwg PO-127-B - We cannot locate N2 isolation valves IN-91 thru 1N-94.
These may be mis-numbered on submittal. They should be N-105, 106, and 107. Confirm and correct technical specification as required.
RESPONSE
a) Valve IRC-66 is the power operated relief valve as distinguished from the other two code relief valves. This valve perfor=s no specific safety function and does not have specific leakage require-ments ocher than the Technical Specification primary coolant leakage requirements. It is not considered that this valve should require testing.
b) Check valve HP-194 has been included in the test program as indicated in - the attached revised table.
c) Power operated valves 29-2 and BS-4 have been included in the test program as indicated in the attached revised table.
d) The current Oconee Technical Specifications require the testing of valves BS-14 and BS-19 at five year intervals. Due to the difficulty in obtaining accessibility in verifying instrument air flow through the spray nozzles, it is considered that this test is not practical at more frequent intervals. Since these valves are not subjected to liquids and are not in a corrosive atmosphere, it is considered that this test interval is ratisfactory.
e) All sixteen main steam safety valves will be tested as indicated on the revised valve table.
f) Valves IN-91 thru 1N-94 were included by error. The correct valves should be 1N-106 and 1N-107. Valve IN-105 does not require testing as it performs no isolation function.
I 4
ATTACHMENT 4
" Proposed Technical Specification Revision, Inservice Inspec-tion" Comments QUESTION 1.
Because of difference in the date of start of facility commercial opera-tion for Oconee Units 1, 2 and 3, we recommend that separate Technical Specification be established for each unit.
RESPONSE
Oconee Unit I was required to conform to the provisions of 10CFR50.55a beginning November 15, 1977. Oconee Units 2 and 3 will be required to meet these criteria on January 9,1978 and April 16, 1978, respectively.
The October 1, 1976 submittal provided proposed Technical Specifications amendments which were designed to separate the surveillance requirements of Oconee 1 and Oconee 2,3.
In the future, after Oconee 2 and 3 meet the criteria of 10CFR50.55a, the Technical Specifications language should be general enough to permit common usage for all three Oconee units.
QUESTION 2.
The language in the Technical Specifications 4.04 and 4.2.1 is not acceptable. The sample technical specification language recommended in the letter from R.
?urple, Chief, Operating Reactors Branch #1, NRC to Duke Power Compa-,, dated April 26, 1976 should be used, i.e.,
4.2.1 - Inservice inspection of ASME Code Class 1, 2 and 3 cocponents shall be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10CFR50, Section 50.55a(g), except where specific written relief has been granted by the NRC pursuant to 10CFR50, Section 50.55a(g)(6)(1).
4.0.4 - Inservice testing of ASME Code Class 1, 2 and 3 pumps and valves shall be performed in accordance with Section XI ef the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10CFR50, Section 50.!5a(g), except where specific written relief has been granted by tDe NRC pursuant to 10CFR50, Section 50.55a(g)(6)(1).
RESPONSE
The provisions of 10CFR50.55a(g)(1) require that Oconee 1 meet the inservice inspection requirements of paragraphs (g)(4) and (g)(5) to the extent practi- -
cal. Paragraph (g)(4) requires that " components classified as ASME Code Class 1, 2 and 3 shall meet the requirements except design and access pro-visions and preservice examination requirements......that become ef fective subsequent to editions......in paragraph (b) of this section to the extent practical within the limitations of design, geometry and materials of construction of the components".
Paragraph (g)(5)(1) requires the licensee to revise the inservice inspection program, as necessary, to meet the provisions of paragraph (g)(4).
Paragraph (g)(5)(ii) requires that License Amendments be submitted at least
-six months before the start of a period if the revised inservice inspection program conflicts with the Technical Specifications of the facility.
Paragraph (g)(S)(iii) makes provisions for the licensee to notify the Cocsission if it is determined that conformance with certain code require-ment is impractical.
Finally, Paragraph (g)(5)(iv) requires that where an examination or test requirement by the code is determined to be impractical by the licensee and is not included in the revised inservice inspection program, the basis shall be demonstrated to the satisfaction of the Commission not later than 12 months after the expiration of the initial 120 month period of operation.
As can be seen from the above su=marization of the regulations, the licensee is required to perform an inservice inspection program in accor-dance with the ASME Code which becomes in effect to the extent practical within the limitations of design, geometry, and materials of construction of the components.
If conflicts exist between the inservice inspection program and the Technical Specifications, a license amendment resolving the conflict shall be su' mitted six months prior to the start of the inspection interval. Further, if it is determined that conformance with certain provisions of the code are impractical, the licensee shall notify the Commission and shall demonstrate this to the satisfactiGn of the Co= mission within 11 years from the start of the inspection interval.
It is our understanding of the regulations that Commission approval of the inservice inspection program is not required prior to the start of an interval unless a conflict exists with the Technical Specifications.
Specific written relief must be granted by the NRC within 11 years.
Therefore, the proposed Oconee Technical Specifications which cite the regulations and require that the testing and examinations be performed to the extent practicable within the limitations of design, geometry and materials of construction are adequate and properly implement the regula-tion. Additionally, if the standard wording were adopted and written
. relief was not received from the Commission prior to the start of the interval, we would be in a situation of noncompliance.
It should also be noted that the regulations do not require submittal of a description of the inservice inspection program every 40 months and the pump and valve testing every 20 months unless specific relief is requested.
It is considered that the ir. formation requested by Appendix A to Mr.
A. Schwencer's letter dated November 30, 1977 is unnecessary after the initial submittal.
QUESTION 3.
Technical Specifiation 4.2.6 regarding the pump flywheel inservice inspection program is not acceptable. We require that a surface examination of all exposed surfaces and a complete volumetric exami-nation, during the plant shutdown coinciding with the inservice inspection schedule as required by the Section XI Code be performed at approximately ten-year intervals, in addition to the in-place volumetric examination of the bore and keyway of each reactor coolant pump flywheel at approximately three-year intervals as specified in Technical Specification 4.2.6.
Removal of the flywheel is not required.
RESPONSE
The following wording is proposed for the pump flywheel inservice inspection program:
4.2.6 Reactor coolant pump flywheels shall be examined as follows. An inplace volumetric examination of the bore and keyway shall be performed at approximately three-year intervals coinciding with ASME Section XI inservice inspection examinations. Additionally, a surface examination of all exposed surfaces and a complete ultra-sonic volametric examination of the flywheel shall be conducted at approximately ten-year intervals coinciding with ASME Section XI Inservice inspection examinations.
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OCONEE UNIT 1 CONFOIOfANCE WITl! ASME SECTION XI, SUBSECTION IWV E
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DRAWING NO~
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$ES
$ES
$3 Valve No.
Valve Name e
nv na naw nmx x
- o. :s Comments PO-100A-1_
1RC-67 Pressurizer Relief R
X C
1RC-68 Pressurizer Relief R
X C
PO-101A-1 lilP-24 A IIPI Pump Suct. From BWST P
X B
1HP-25 C llPI Pump Suct. From BWST P
X B
litP-101
~ A IIPI Suct. Check Viv.
C X
C 1
litP-102 C llPI Suct. Check Viv.
C X
C 1
lilP-105 A IIPI Disch. Check Vlv.
C X
C litP-109 B llPI DIsch. Check Vlv.
C X
C lilP-113 C llPI Disch. Check Vlv.
C X
C ICA-85 BAMT to LDST C
X C
ICA-73 CBAST to LDST C
X C
lilP-16 Makeup to LDST P
X B
ILP-57 LPI to llPI C Train C
X C
1 l ILP-55 LPI to llPI B Train C
X C
1 PO-101B-1 lilP-3 A LD Cooler Outlet P
X X
A/B 111P-4 B LD Cooler Outlet P
X X
A/B litP-5 LD Coolet Isolation P
X X
A/B li!P-20 RC Pump Seal Return P
X X
A/B 1.2 111P-21 RC Pump Seal Return P
X X
A/B 1
lilP-26 A Loop Injection P
X B
litP-27 11 Loop Injection P
X B
lilP-188 B Loop Check Valve C
X C
1 111P-153 B Loop Check Valve C
X C
1 litP-152 B Loop Check Valve C
X C
1 l 111P-194 A Loop Check Valve C
X C
1 PO-102A-1 1CF-3 A CFT Sample / Drain P
X A
2 1CF-4 B CFT Sample / Drain P
X A
2 -
I OCONEE UNIT 1 CONFORMANCE WITil ASMC SECTION XI, SUBSECTION IWV l
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DRAWING NO E$
Valve No.
Valve Name e
nw nm nmx nmw w
- o. :s Comments ICF-7 CFT to MWilUT M
X A
E X
ICF-2 B CFT Isol Valve P
E X
E X
ICF-6 B CFT Vent P
E X
ICF-ll A CFT Disch Check Viv.
C X
C 1
C X
C 1
C X
C 1
C X
C 1
X A
2 1CF-33 CFT Vent to Vent lidr.
M X
A 2
?CF-35 CF'r Vent to WG Filter M
X A
M X
A ILP-1 Dil Isolation Valve P
X B
1
'ILP-2 Dil RB Isolation Valve P
X B
1 1LP-3 Dll RB Icolation Valve P
X B
ILP-6 LPI Suction XConn P
X B
ILP-7 LPI Suction XConn P
X B
ILP-9 LPI Disch XConn P
X B
11.P-10 LTI Disch XConn P
X B
lLP-12 LI - A Cooler Outlet P
X B
ILP-14 LF' B Cooler Outlet P
X-B 1LP-17 LPs. A RB Isol. Viv.
P X
P X
X B
X B
ILP-21 BWST to LPI Suct.
P X
B ILP-22 BWST to LPI Suct.
P X
B ILP-29 BWST to A LPI !!dr.
C X
C ILP-30 BWST to B LPI Ildr.
C X
C D,P-31 A LPI Pump Disch C
X C
ILP-33 B LPI Pump Disch C
X C
ILP-51 Caustic Addn.
M X
B ILP-28 BWST Isolation M
E X -
OCONEE UNIT 1 CONF 0!iMANCE WIT!! ASME SECTION XI, SUBSECTION IWV E
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DRAWING NO.
H HM HN HI$
HIO E oo kah Valve No.
Valve Name Conenents o
ILP-47 A LPI !!dr. Check V1v.
C X
C 1
ILP-48 B LPI Ildr. Check Viv.
C X
C 1
ILP-103 Boron Dilution Vlv.
P X
B 1
ILP-104 Boron Diltulon Vlv.
P X
B 1
ILP-105 Baron Dilution Viv.
P X
B 1
ILP-15 LPI A Ildr. to llPI P
X B
X B
IBS-5 A RBS Check C
X C
ll!S-6 B RBS Check C
X C
X C
X C
IBS-3 A RBS Suct.
P X
P X
B
[ PO-103A-1 1 11 S - 1 A RilS RB Isol. Valve P
X B
X B
X C
lilS-14 A RBS Disch. Check C
X C
X C
X C
1
[ PO-104A-1 Will be tested every 5 y ISF-60 Fuel Transfer Canal Fill M
X A
2 ISF-61 Fuel Transfer Canal Fill M
X A
2 PO-106-A-1 1CS-64 CBAST Outlet P
X B
PO-106E-1 IFW-64 Filtered Water to RB M
X A
2 1FW-65 Filtered Water to RB M
X A
2 1DU-155 DW to RCP Seal Vent C
X X
A/C 1,2,3 1DW-156 DW to RCP Seal Vent C
X X
X A
2
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OCONEE UNIT 1 CONFORMANCE WITil-ASME SECTION XI, SUBSECTION IWV E
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DRAWING NO*
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$7$
$7$
$3 Valve No.
Valve Name e
n re na nmx nay v
X A
P X
X A/B 2
P X
X A/B ICS-12 QT Recire. Check C
X X
A/C 1,3 1CS-11 QT Recirc. Check C
X X
A/C 3-ICWD-12 QT Vent P
X X
A/B 2
1CWD-13 QT Vent P
X X
A/B PO-107B-1 ILWD-1 Normal Sump Suct.
P X
X A/B ILWD-2 Normal Sump Suct.
P X
X A/B 2
PO-107D-1 ILWD-99 RB Sump to LAWT M
X A
2 PO-110A-1
.CA-17 BAMT to Makeup Filters C
X C
1CA-18 BAMT to Makeup Filters M
X B
ICA-39 Caustic to LP Suction M
X B
IRC-5 Press. Steam Sample P
X X
A/B IRC-6 Press. Water Sample P
X X
A/B 1RC-7 Press. Sample P
X X
X X
A/B IFDW-106 OTSC A Sample P
X X
A/B IFDW-107 OTSC B Sample P
X X
A/B 1FDW-108 OTSC B Sample P
X X
A/B PO-116A IPR-1 RB Purge Outlet P
X X
A/B IPR-2 RB. Purge Outlet P
X X
A/B IPR-7 RB Radiation Monitor P
X X
A/B IPR-8 RB Radiation Monitor P
X X
A/B
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OCONEE UNIT 1 CONFORMANCE WITl! ASME S"CTION XI, SUBSECTION IWV E
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DRAWING NO H"
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Va1ve No.
Valve Name a
ny na naw naw x
- o. :s Comments IPR-9 RB Radiation Monitor P
X X
A/B 1PR-10 RB Radiation Monitor P
X X
A/B lPR-6 RB Purge Inlet P
X X
A/B IPR-5 RB Purge Inlet P
X X
A/B PO-121A-1 IFDW-93 EFDW OTSG A C
X C
1 IFDW-95 EFDW OTSC B C
X C
1 PO-121B-1 IFDW-101 EFDW to OTSG A C
X C
1 IFDW-99 EFDW to OTSG B C
X C
X B
1 li'DW-36 EFDW to OTSC A P
X B
1 IFDW-38 EFDW to OTSG A P
X B
1 IFDW-42 EFDW to OTSG B P
X B
1 IFDW-45 EFDW to OTSG B P
X B
1 IFDW-47 EFDW to OTSG B P
X B
1 IFDW-104 OTSG B Drain P
X X
A/B,
_2 _
1G-23 OfSG B Drain M
X A
2 FDW-103 OTSC A Drain P
X X
A/B 2
2G-23 OTSC A Drain M
X A
2 PO-122A-1 IMS-1 thru Main Steam Relief R
X C
IMS-16 PO-124B ILPSW-6 LPSW to RC? 011 Coolers P
X X
A/B
'l ILPSW-15 LPSW from RCP Oil Coolers P
X X
A/B 1
ILPSW-18 LPSW to RBCU A P
X B
ILPSW-21 LPSW to RBCU B P
X B
ILPSW-24 LPSW to RBCU C P
X B
ILPSW-4 LPSW Dil Cooler Outlet P
X B
ILPSW-5 LPSW Dll Cooler Outlet P
X B
ILPSW-75 LPSW Dil Cooler Outlet C
X C
ILPSW-76 LPSW Dil Cooler Outlet C
X C
lLPSW-251 LPSW Dil Cooler Outlet P
X B
ILPSW-252 LPSW Dil Cooler Outlet P
X B
1LPSW-108 RBCU Outlet M
E X
OCONEE UNIT 1 CONFORMANCE WITil ASME SECTION XI, SUBSECTION IWV E
m n
s E
A4 m
H H"
H H
H 0 0 DRAUINC NO*
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$3 Valve No.
Valve Name a
nr na naw naw w
- o. :s Comments PO-127B IN-106 N2 Isolation M
X A
2 IN-107 M
X A
2 IN-116 M
X A
2 IN119 M
X A
2 1CA-27 M
X A
2 1CA-29 M
X A
2 IN-130 M
X A
2 IN-129 H
X A
2 PO-137 IBA-5 BA Isolation Valve M
X A
2 IBA-33 BA Isolation Valve.
M X
A 2
X X
X X
A/C 1,3 1CC-76 CC to CRD Service Structure C
X X
A/C 1,3 10C-77 CC to CRD Service Structure C
X X
X X
X X
A/B 1
0-472 lIA-90 Inst. Air to RB M
X A
2 IIA-91 Inst. Air to RB M
X A
2 0-472 ILRT-24 Leak Rate Test M
X A
2 ILRT-25 Leak Rate Test M
X A
2 ILRT-38 Leak Rate Test M
X A
2 ILRT-39 Leak Rate Test M
X A
2 lLRT-17 Leak Rate Test M
X A
2
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Valve Type R - Relief valve P - Power-operated valve, electric or pneumatic C - Check valve M - Manual valve Leak Test X - Required Safety Valve Tect X - Required Check Valve Test X - Required Locked Open or Closed X - Required to be locked open or closed during power operation Comments 1 - Valve cannot be exercised during power operation 2 - Provisions for leak testing valve do not exist due to piping configuration 3 - Provisions for exercising valve do not exist 9
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