ML20096F297
| ML20096F297 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 05/14/1992 |
| From: | Beck G PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| GL-89-04, GL-89-4, NUDOCS 9205210007 | |
| Download: ML20096F297 (4) | |
Text
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,7 PIIILADELPIIIA' ELECTRIC COMPANY
. NUCLEAR GROUP HEADQUARTERS -
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- 955-65 CHESTERBROOK BLVD, WAYNE. PA 19087 5691 (215) 640-6000 t
NUCLEAR ENGINEERINO & SERVICES DEPAKTMENT May_14, 1992 Docket Nos. 50-277-50-278 License Nos. DPR-44:
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DPR-56 U.S. Nuclear-Regulatory Commission 4:
Attn:
Document Control' Desk Washington,-DC._20555-
-SUBJECT!
Peach Bottom 1 Atomic Power Station, Units 2 and 3 InservicecTesting Program REFERENCES-(1)_ Letter from J.-W.
Gallagher (PECo)Lto!W. R.
Butler (NRC),-; dated. June 29,--1988-
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'2)-Generic Letter 89-04, " Guidance-on. Developing.
Acceptable Inservice Testing Programs",' dated A p r i l 3,---.1 9 8 9 (3) "_ Minutes.on the Public-Meetings 4on Generic Letter 89-04",-. dated October 25',1989-(4) Letter from W.,'R.0 Butler ~(NRC) to;G.sJ.: Beck (PECo),_ dated January' 17,.119911 f
(5) Letter fromiW..R. Butlerf(PECo)-to NRC, dated October 8,11991 (6). Letter from A. R. - Blough r (NRC)1 to D. : M. Smith
_(PECo), "CombinedLInspection" 50-277/92-07 and 50-278/92-07",jdat'ed April 116,f1992 i
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Dear.' Sir:
In: Reference (1),(PhiladelphiacElectric; Company-(PECo) submittedia' revised-second:10 yearfinterval7 Inservice;Te_stinge (IST) Program 1for Peach; Bottom. Atomic'PowerJStationV(PBAPS),
U n i t s-s 2-a n d 1:3.
- In
- Referencec(4),pthe_NRC transmitted a.Safetyi Evaluation!of'the?IST Program.1 fin; Reference (5),LPECo;provided:7
- an updatedi; uncontrolled.; copy ofLRevision12 to the;IST" Program <
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.which included.changesirecommended-by4the!NRC in"theiSafety=
5 Evaluation.
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>PDR' ADOCK-05000277-
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-9205210007 920514.
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'. Locument Control Desk May 14 1992 PB Inservice Testine Srogram Pago 2 The purpose of this letter is to submit for your information only, a copy of new Rol19f Request GVRR-6, Revision 0 (Attached)..
New Relief Request GVRR-6 lists in a single location all the PBAPS Units 2 and 3 check valves that are included in the check valve sample disassembly and inspection program which has been implemented in accordance with the guidance provide in Generic Letter 89-04 (Reference 2), Attachment 1, Position 2
(" Alternative to Full Flow Testing of Check Valves").
Currently, the valves included in GVRR-6 are also listed in'NRC approved Relief Requests 10-VRR-1, 13-VRR-1, 14-VRR-1, 14-VRR-3, and 23-VRR-1.
As a result of this new Relief Request, Relief Request 10-VRR-1, 13-VRR-1, 14-VRR-1, 14-VRR-3, and 23-VRR-1 will be deleted from the IST-Program.
We note that this new Relief Request is being submitted for your information only and.not for reviewLand approval.
As stated in Reference 3,
"(1)n cases where a generic 11etter position that approves an alternative to the ASME' Code is being followed, a relief request is not required, but.the deviation from the Code should be documented in the IST program along with its method of approval (i.e.,
throagh the relevant generic letter-position)."
This Relief Request satisfies this position.
During a recent NRC Inspectirn (Reference.6), PECo committed tu the Inspector to submit this new Relief Request by May 19, 1992.
This letter satisfies this commit ment.
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If you have any questions, please contact us.
Very truly yours, G.
Beck, Manager Licensing Section Attachment cc:
T. T. Martin, Administrator,-Region I, USNRC J. J. Lyash, USNRC Senior Resident. Inspector, PBAPS 1
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PBAPS 2 & 3,-IST Prtgram Sp;c. M-710 App;ndix C RELIEF REQUEST No. GVRR-6, REVISION 0 Valve (s)
CHK-2-10-019A,B.C,D CHK-3-10-019A.B,C,D CHK-2-10-21541 CHK-3-10-31541 CHK-2-10-21577A,B CHK-3-10-31577A,B, CHK-2-13-029 CHK-3-13-029-CHK-2-14-023A.B.C,D CHK-3-14-023A,B,C,D CHK-2-14-066A,B.C,D CHK-3-14-066A,B,C,D CHK-2-14-29036A,B CHK-3-14-39036A.D CHK-2-14-29051A,B CHK-3-14-39051A,B-CHK-2-23-062 CHK-3-23-062 ategory C
Testing Requirement (s): Exercise in the reverse direction.
Basis for Relieft The above valves all perform a safety function in the reverse direction.
Because of system configura tion,:.L these - valves cannot be verified closed using visual verification, system parametors or by leak testing methods. Valve disassembly will be required to verify reverse direction closure, disasssmbly of the valves,- if attempted at cold shutdown, could result in a delayed plant start up.
Alternate Testingt Reverse flow closure will-be verified at refueling by check
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valve disassembly - rnd inspections partial. stroke will be performed af ter valve reassembly.
A check valve ~ sample Misassembly and inspection program is
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imp'.emented in accord.nc6 with the' NRC guidance provided_ in Gen.ric letter 39-04, -Attachment 1,
Position - 2 'and is ddumented in-Section 5.'4.2 of the IST:- Program' text. -This vample program grouns valves that are of the same design, have the same service condition. -and -have the orientation.
- same valve-At least one valve from eac'- group shall: be tested during each-refueling outage, and each va'.ve will be tested at least once every six years.
If the disassembled valve is unable to be full stroke e.;ercised, or is binding, or. failure f the valve -
internals is observed, the valve : shall = be refurbished a s --
necessary and the - remaining val /es in the group shall be disassembled, inspected, and manually full st, ie exercised.
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