ML20079A941

Application for Amends to Licenses NPF-68 & NPF-81,revising Ts,By Revising Leak Test Frequency for Valves W/Resilient Seals

ML20079A941
Person / Time
Site:	Vogtle
Issue date:	12/27/1994
From:	Mccoy C GEORGIA POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20079A943	List: ML20079A941 ML20079A950
References
LCV-0483, LCV-483, NUDOCS 9501040198
Download: ML20079A941 (8)

Text

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T Georg:a Power Company 40 inverness Center Parkway

-* Post Offce Box 1295 Birmingharn, A12ama 35201 Teler/ sono 205 877-7122 C. K. McCoy Georgia Power Vce Prescent. Nuclear Vogtie Proiect CaCember 27, 1994 ire sourren eurre system LCV-0483 Docket Nos. 50-424 50-425 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555 Gentlemen:

VOGTLE ELECTRIC GENERATING PLANT REQUEST TO REVISE TECHNICAL SPECIFICATIONS REVISION TO LEAK TEST FREOUENCY FOR VALVES WITH RESILIENT SEALS In accordance with the provisions of 10 CFR 50.90 and 10 CFR 50.59, Georgia Power Company (GPC) hereby proposes to amend the Vogtle Electric Generating Plant (VEGP)

Unit I and Unit 2 Technical Specifications, Appendix A to Operating Licenses NPF-68 and NPF-81. The revision will change the period for conducting leak testing of containment purge valves to every refueling outage.

During the initial licensing of VEGP there was insuflicient experience with large containment isolation valves utilizing resilient seals to demonstrate that the seals would not degrade within the two year test interval required by 10 CFR 50 Appendix J.

Consequently GPC agreed to more frequent testing of these valves and the Technical Specifications included a quarterly test requirement. Since that time (1987) the valves have been routinely tested every three months and no indication on seal degradation has been observed. Therefore GPC is requesting that the Technical Specifications be amended to require a test interval of once per refueling outage which meets the 10 CFR 50 Appendix J requirements. This change is consistent with the test interval subsequently approved by the NRC for similar valves using resilient seat material on other operating i plants.

The frequent testing of these valves requires extensive work inside the reactor containment during operation, with the consequential radiation exposure and risks associated with erection and removal of scaffolding and installation and removal of flanges. The approval of this change to the Technical Specifications will reduce the required activities inside the containment during plant operation. This is a Cost Beneficial Licensing Action (CBLA) and it is estimated that this change will save about 750 manhours between refueling outages per unit.

Georgia Power Company requests that this revision be approved by June 1,1995.

ir' i 950104o198 941227 l i

PDR ADOCK 05000424 P PDR

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' GeorgiaPower1 U. S. Nuclear Regulatory Commission LCV-0483 The proposed change and the bases for the changes are described in enclosure 1 to this letter. Enclosure 2 provides an evaluation pursuant to 10 CFR 50.92 showing that the proposed changes do not involve significant hazards considerations. Instructions for l

incorporation of the proposed changes into the technical specifications and a copy of the changes are provided in enclosure 3.

In accordance with 10 CFR 50.91, the designated state 00icial will be sent a copy of this letter and all enclosures.

Mr. C. K. McCoy states that he is a vice president of Georgia Power Company and is authorized to execute this oath on behalf of Georgia power company and that, to the best of his knowledge and belief, the facts set forth in this letter and enclosures are true.

GEORGIA POWER COMPANY By: .

C. K. McCo Sworn to and subscribed before me this ay of [d .1994.

I6mulM Notary Pubhc

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Enclosures:

1. Basis for Proposed Change

2. 10 CFR 50.92 Evaluation

3. Instructions for Incorporation and Revised Pages c(w): Georgia Power Company Mr. J. B. Beasley, Jr.

Mr. M. Sheibani NORMS U. S. Nuclear R_rgulatorv Commission ,

Mr. S. D. Ebneter, Regional Administrator l Mr. D. S. Ilood, Licensing Project Manager, NRR 1 Mr. B. R. Bonser, Senior Resident Inspector, Vogtle l State of Georgia Mr. J. D. Tanner, Commissioner, Dept. of Natural Resources

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ENCLOSURE 1 VOGTLE ELECTRIC GENERATING PLANT REQUEST TO REVISE TECHNICAL SPECIFICATIONS REVISION TO LEAK TEST FREQUENCY FOR VALVES WITH RESILIENT SEALS B ASIS FOR PROPOSED CHANGE Proposed Change The proposed change to the Technical Specifications (TS) will change specification 4.6.1.7.2 from " At least once per 3 months the containment purge valves with resilient material seals in each sealed closed containment purge supply and exhaust penetration shall be demonstrated operable.. " to "At least during each refueling outage the i containment purge valves with resilient material seals in each sealed closed containment i purge supply and exhaust penetration shall be demonstrated operable.. ", and delete the phrase " ..will provide early indication of resilient material seal degradation and.. " from bases section 3/4.6.1.7.

Blis During the initial licensing of the Vogtle Electric Generating Plant the NRC staff expressed concerns about seal degradation for large isolation valves having resilient seats.

In response to this concern Georgia Power Company and the stafragreed to a program of accelerated testing for these valves. Georgia Power believes that the concern was based on the lack of confidence in the performance of resilient seats and that the intent of the accelerated testing program was to determine ifincreased testing was needed on a permanent basis. Georgia Power Company has conducted quarterly tests on these valves since 1987 and has determined that seal degradation does not occur. Based on the results of these tests we have concluded that increased testing is not required on a permanent basis and that the history of these valves supports a test intervalin accordance with 10 CFR 50 Appendix J. The results of the tests are tabulated in table 1-1 which demonstrates that the measured leak rates have consistently been well below the allowable leakrate (26,320 SCCM) and that there were no instances ofincreased leakage due to degradation of resilient seats. Figure 1-1 provides a schematic of the valve arrangement and identifies the valves referenced in table 1-1. The conclusions about the performance of the resilient seat material and the revision to the testing frequency is consistent with the findings of the NRC stafTon other operating plants.(See SER for Amendment 54 to operating license DPR-18, TAC number M77849) Since the leak test requires the construction of ,

scaffolding and installation of flanges, the change to the frequency will significantly reduce  ;

I the level of required activity inside containment during plant operation by allowing the tests to be conducted during refueling outages.

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TABLEl-1 VEGP CONTAINMEhT PURGE VALVES rn~ -- ,.w

1l NIT-1 TEST DATAL PENETRATION #83 PENETRATION #84 .

DATE Ill%2626A Il!V2626B 1HV2627A ll!V2627B NOTES DATE IIIV2628A IIIV2628B llIV2629A liiV2629B NOTES 24* IRC 14* IRC 24* ORC 14' ORC 24"IRC 14* IRC 24" ORC 24' ORC 08/2417 162.00 162.00 162.00 162.00 1 08/22187 172.00 172.00 172.00 172.00 1 11/2017 610.00 610.00, 610.00 610.00 1 11/20/S7 39.20 39.20 39.20 39.20 1 02/13!B8 241.90 241.90j 241.90 241.90 1 02/14/88 23930 23930 23930 239.30 1 0602/88 344 00 344.00 344 00 344 00 1 05'20,18 390.00 390.00 390.00 390.00 1 08'2318 141.70 141.70 141.70 141.70 1 08/1918 128.70 128.70 128.70 128.70 1 1Ii17/88 200 00 200 00 200.00 200 00 1 I!!!7/88 1 % 60 196.60 196 60 1%.60 1 12/I4/88 43.20 34 60 1132.00 1132.00 12!!418 37.20 32.40 1280.00 1280.00 02/13/89 856 856 856 856 2 0308.19 150.00 22 00 401.00 401.00 0396'89 12.00 24.60 327.00 327.00 06>Vl/89 1453.00 18.05 506.00 506 00 0696'89 580.00 101.20 783.00 783.00 08/30.89 2450 00 72.80 3140.00 3140 00 08/31.'89 9430 32.60 795.00 795.00 1!!!4/89 1II2.00 79.20 709.00 709.00 11/15/89 95.50 47.20 506.00 506.00 02/20.90 1070.00 53.70 570.00 570 00 02/2190 350 00 53.70 720 00 720.00 03/2490 2750.00l 14 30 18.10 18.10 03/2390 57.40 34.50 56 80 56.80 06/20.90 3900.00 25.80 134.40 134 40 06/20 90 36.40 1012.00 1061.00 1061.00 09/11.90 410.00 84 60 1202.00 1202.00 09il2.90 862.00 57.00 1181.00 1181.00 12/18.90 2260 00 35 00 297.00 297.00 12/19/90 453.00 44.00 283.00 283.00 02'2691 12070 00 115.80 843.00 843.00 3 02/27/91 515.00 42.50 543.00 543.00 02'27/91 850.00 RETT.ST 05/2191 316 00 86.60 794 00 794 00 05/22.91 8150.00 134.00 455.00 455.00 5 079391 873 121.8 438 438 REEST 08/13,91 230 6 E2 122 081491 275 72.1 1320 1320 119491 91 3 16.1 383 383 4 119291 6200 1353 1770 1770 3 119791 65.7 RETEST 01,22.92 565 11.1 520 $20 Ol/2992 1400 57.4 1420 1420 04/21/92 142 47 470 470 04'22.92 780 82.6 1370 1370 07/1992l 69.1 446 517 517 07/1592 324 18 285 285 109692 470 59 611 611 1007.92 227 23.8 608 608 0195=93 43 8 223 698 698 0196.93 260 282 940 940

( C3/18/93 6380 38 345 345 03/1893 50.6 6.2 436 436 04'19 93 201000 42.5 461.5 461.5 3 04/1993 317 56.2 74.7 74.7 f

( 0400.93 89 3 RETEST i 06/15.93 159 95 706 706 06/1693 674 36.8 65.1 65.1 09 07/93 57.9 6.9 376 376 09.0193 99.2 17 658 658 11/30/93 86.5 183 672 672 12.91/93 49.1 3.2 727 727 NOTE 1: RST PERFORMED DETWEEN INDOARD AND OUTBOARD VALVES. TOTAL LEAKAGE RECORDED.

NOTE 2: SPECIAL TEST TO COMPARE DEDVEEN VALVE EST AND TESTING FROM ACCIDENT FLOW DIRECTION.

NOTE 3: RETESTED DUE TO IIIGli PREVIOUS LEAK RATE. NO VALVE ADJUSTMENTS WERE MADE,EST DOUNDARY LEAKAGE SUSPECT.

NOTE 4; VALVE WOUID NOT PRESSURIZE, VALVE FOUND NOT FULLY CIDSED. OUTAGE POST llRT. RE{IDSED VALVF, TEST PERFORMED SATISFACTORY.

NOTE 5: IIIGil llAKAGE DUE TO LEAK AT BilND FLANGE. RETESTED VALVE %TTli DIFFERENT GASKET MATERIAL IN BLIND F1.ANGE.

TAIM l 1 (CONTINUED)

VEGP CONTAINMENT PURGE VALVES e--mew -n e n

[M9 TESTRATAy PENETRATION #83 PENETRATION #84 .

DATE 211V2626A 21 V2626B 211V2627A  : LIV 2627B NOTES DATE 211V2628A 211V2628B 211V2629A 21tV2629B NOTES 24* 1RC 14* IRC 24* ORC 14* ORC 24* IRC 14* IRC 24* ORC 14* ORC 08/1049 638 00 34.10 700.00 700.00 08/1049 280.00 808.00 1562.00 1562.00 11/01/80 338.00 150.00 3500.00 3500.00 11/02/89 335.00 91.90 6010.00 6010.00 0207S0 240.00 174.00 737.00 737.00 02/0&90 440.00 108.00 191.00 191.00 04/1890 269.00 244.00 138.00 138.00 04/20/90 1103.00 863.00 1008.00 1008.00 07/10SO 162.90 62.10 922.00 922.00 07/10M0 425.00 42.00 7.00 7.00 10/22/90 178.40 46.90 23.00 23.00 10/23/90 578.00 108.00 672.00 672.00 0I/249I 64.30 20.40 227.30 227.30 01/249I 560.00 65.80 5700.00 5700.00 1 03/2161 472.00 RETEST 04/1791 334.00 30.00 433.00 433.00 04/17/91 284.00 68.80 433.00 433.00 07/0991 92.40 74.60 491.00 491.00 07/10S 1 87.00 50.00 1150.00 1150.00 259.00 81.00 783.00 783.00 10/0491 435.00 29.00 1796.00 1796.00

_1042/91 0107S2 3120.00 2740.00 4550.00 4550.00 01/08/92 526.00 101.30 910.00 910.00 04/1552 36.30 255.00 38.40 38.40 04/16/92 1186.00 85.40 519.00 519.00 07/0762 2;8.00 34.60 36.50 36.50 0708S2 111.20, 60.70 274.00 274.00 09/30S 2 275.00 33.40 187.00 187.00 09/30/92 290.00] 38.00 457.00 457.00 12/17/92 6.00 46.10 168.70 168.70 12/17/92 460.00 130.00 635.00 635.00 03/12S3 132.00 27.00 55.00 55 00 03/18/93 112.00 6.00 157.00 157.00 06S2N3 410.00 623.00 582.00 582.00 06/03/93 114.00 54.00 89.00 89.00 10/12/93 152.00 12.00 32.00 32.00 10/12/93 67.20 38.50 65.80 65.80 01/26/94 272.00 659.00 547.00 547.00l , 01/27/94 10.00 13.60 283.00 263.00 NOTE 1: RETESTED DURING FORCED OUTAGE DUE TO PREVIOUS IIIGII LEAKAGE RATE.

Enclosure 1 (Continued)

FIGURE 1-1 Containment Purge Supply / Exhaust Penetration Typical Arrangement INSIDE CONTAINMENT i OliTSIDE CONTAINMENT i

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w ENCLOSURE 2 VOGTLE ELECTRIC GENERATING PLANT REQUEST TO REVISE TECHNICAL SPECIFICATIONS REVISION TO LEAK TEST FREQUENCY FOR VALVES WITH RESILIENT SEALS 10 CFR 50.92 EVALUATION Pursuant to 10 CFR 50.92, Georgia Power Company (GPC) has evaluated the proposed revision to the Technical Specifications and has determined that operation of the facility in accordance with the proposed amendment would not involve any significant hazards considerations.

GPC has concluded the following concerning:

1. The proposed change to the Technical Specifications does not involve a significant increase in the probability or consequences of an accident previously evaluated because the tests results have demonstrated that the resilient seat material does not degrade and cause containment isolation valves to leak. Therefore the valves will perform as assumed in the accident analyses.

2. The proposed change to the Technical Specifications does not create the possibility of a new or different kind of accident from any accident previously evaluated because it does not require the valves to function in any manner other than that which is currently  ;

required.

3. The proposed addition to the Technical Specifications does not involve a significant reduction in a margin of safety because it only aiTects the frequency of the test and does not change the leakage acceptance criteria. Since suflicient data has been l collected to demonstrate that the resilient seals do not degrade, testing at the same frequency as other containment isolation valves will not reduce the margin of safety provided by the Technical Specifications.

i Based upon the preceding information, it has been determined that the proposed Technical Specifications addition does not involve a significant hazards consideration as defined by 10 CFR 50.92.

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ENCLOSURE 3 VOGTLE ELECTRIC GENERATING PLANT REQUEST TO REVISE TECHNICAL SPECIFICATIONS REVISION TO LEAK TEST FREQUENCY FOR VALVES WITH RESILIENT SEALS INSTRUCTIONS FOR INCORPORATION The proposed change to the Vogtle Electric Generating Plant Technical Specifications would be incorporated as follows. ,

Remove Page Insert Page ,

3/4 6-11* and 3/4 6-12 3/4 6-11* and 3/4 6-12 '

B 3/4 6-3 and B 3/4 6-4* B 3/4 6-3 and B 3/4 6-4*

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• Overleaf page containing no change.

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