ML20096F974

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Application to Amend License DPR-71,revising Tech Specs to Allow One Time Only Deferment of Required Type B & C Local Leak Rate Tests Until 850331 Refueling Outage.Fee Paid
ML20096F974
Person / Time
Site: Brunswick Duke Energy icon.png
Issue date: 09/04/1984
From: Cutter A
CAROLINA POWER & LIGHT CO.
To: Vassallo D
Office of Nuclear Reactor Regulation
Shared Package
ML20096F975 List:
References
NLS-84-371, NUDOCS 8409100296
Download: ML20096F974 (6)


Text

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CD&L Carolina Power & Light Company SEP-0 41984 SERIAL: NLS-84-371 s

Director of Nuclear Reactor Regulation Attention: 'Mr. D. B. Vassallo, Chief Operating Reactors Branch No. 2 Division of Licensing United States. Nuclear Regulatory Commission Washington, DC 20555 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NO..I DOCKET NO. 50-325/ LICENSE NO. DPR-71 REQUEST FOR LICENSE AMENDMENT'AND EXEMPTION FROM 10 CFR 50, APPENDIX J EXTENSION OF UNIT 1 LOCAL LEAK RATE TESTS

Dear Mr. Vassallo:

SUMMARY

In accordance with the Code of Federal Regulations, Title 10, Parts 50.90 and 2.101, Carolina Power & Light Company (CP&L) hereby requests a revision to the Technical Specifications (TS) for the Brunswick Steam Electric Plant, Unit No. l'. The proposed change revises section 4.6.1.2.d to allow a one-time only deferment of required Type B and C local leak rate tests (LLRTs) until'the next' refueling outage scheduled to begin on or before March 31, 1985.

Section 4.6.1.2.d r'equires performance of LLRTs at least once per 24 month

~ interval based on the requirements of 10 CFR 50, Appendix J, Section D, Part 2.= Therefore, an exemption-to 10 CFR 50 Appendix J is also requested.

A listing of the valves and penetrations involved in this request, their size (applicable to penetrations only), results of the previous LLRTs, and the These due dates range current test due dates are provided in Attachment 1.

from December 1984 to March 1985. Additionally, Section 4.6.1.2.f is also revised to allow a one-time only deferment of main steam line isolation valve (MSIV) leak testing until the March 31, 1985 refueling outage. The current due date for the MSIV leak testing is March 18, 1985.

DISCUSSION In granting a.similar request to Tennessee Valley Authority for Browns Ferry 2, the NRC stated that the intent of Appendix J was that isolation valves be tested during refueling outages. Carolina Power & Light Company is presently scheduled to conduct a refueling outage for Brunswick-1 beginning on

<or before March 31, 1985. The proposed amendment would allow these tests to be postponed until that refueling outage. Such an extension is desirable in order to maintain personnel exposures as-low-as-reasonably achievable (ALARA). With the current LLRT schedule, mid-cycle LLRT's would need to be performed again early in Brunswick-1 Cycle 5 to return Performance to a schedule which is coincident with the Unit I refueling interval. q AD B409100296 840904 l'

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4 D. L. Vassa11'o of mid-cycle LLRT'sinow and during the next fuel cycle would result in

' increased exposure of personnel of approximately 20 man-rem which is not consistent with CP&L's ALARA policy.

In addition, the NRC stated in its consideration of the TVA request, that the test interval for Type C tests in' Appendix J was based on two years of

-expected exposure-of components to' service conditions. In the case of the valves referred to in our request, approximately eight months of the two year period since-the valves were last tested was spent in an extended maintenance

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outage during which the components were not exposed to an operating environment.

. Technical Specification Section 4.6.1.2.f requires that the main steam line isolation valves be leak tested at least once per 18 months. The MSIVs were last tested on May 3, 1983. Utilizing the maximum surveillance period of 125 percent, the latest required performance date is March 18, 1985. The requested extension results in only an additional 12 days, or a 1.75 percent increase, in the maximum surveillance interval permitted by the TS.

SIGNIFICANT HAZARDS ANALYSIS Carolina Power & Light Company has reviewed this request and determined that, for purposes of a 10 CFR 50.92 definition, a significant hazards consideration may be involved. However, CP&L believes that deferment of the LLRT and MSIV leak test due dates will not result in a significant increase in risk to the public's health and safety for the following reasons:

1. The majority of the tests requiring extensions are for valves and penetrations which are not exposed to harsh environments and typically exhibited satisfactory test results.
2. Subsequent to the last performance of these LLRTs an eight month outage ensued during which the valves and penetrations were not subject to normal operating conditions thus reducing the potential degradation during this period.
3. The TS limit for LLRT leakage is 159.78 SCFH (calculated in accordance with TS section 3.6.1.2). The present recorded LLRT leakage for Brunswick-1 is approximately 58 SCFH below this limit. In addition, the TS limit of 159.78 SCFH is only 60 percent of the total allowable containment leakage calculated using 10 CFR 100 guidelines. Therefore, the present recorded LLRT for Brunswick-1 is approximately 38 percent of that allowed by 10 CFR 100 guidelines.

'4.. Actual containment leakage during a LOCA would require leakage by two valves in series. Most LLRTs are performed between these valves, resulting in greater recorded leakage than would most probably occur during a LOCA.

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!D. B.1Vassallo.

. 5 .- - :Thelincrease in the likelihood'of an increase in the 1.eak rate!for the MSIVs.resulting-from the'12-day-(1.75 percent) increase in the maximum' surveillance-frequency permitted by the TS is minimal.

/ 6.- Previous test results (see

Attachment:

1) indicated leakage h only .one

, . set of MSIVs'. The~ recorded leakage was 4.141-SCFH, only-36 percent of the allowable' leakage-of 11.5 SCFH.'

ADMINISTRATIVE INFORMATION-1 The proposed' revision totthe Brunswick-1 TS is provided in Attachment 2.

' Carolina Power & Light Company has evaluated this request in accordance with

'the provisions of 10 CFR 170.12 and has determined that a license amendment application fee is required. A check for $150.00 is enclosed in payment of.

this fee.

, Should you have - any questions' concerning this submittal, please contact l Mr.~Sherwood R. Zimmerman at (919) 836-6242.

You very t uly, 1

A. B. Cutter - Vice esident Nuclear Engineering & Licensing-ABC/ MAT /pgp.-(473 MAT)

Attachments-cc:Mr. D.-O. Myers (NRC-BNP)

Mr. J. P. O'Reilly.-(NRC-RII)

Mr. M. Grotenhuis=.(NRC)

Mr. Dayne H. Brown-

. Radiation Protection Branch Division of Facility Services Department of Human Resources

'A..B. Cutter, having been first duly sworn, did depose and say that the

!.' -information contained herein is true and correct to the best'of his

- o information, knowledge and belief; and the sources of his information are

. officers, employees, contractors, and agents of Carolina Power & Light

Company.

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Notary (Seal) a My commission expires: sla/a ~

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s ATTACHMENT'1 NixmuM PENETRA- PREVIOUS TION LINE TEST SIZE RESULTS TEST NO. - EQUIPMENT TESTED (INCHES) (SCFH)- TEST DUE DATE

.E-1 X100A ELECTRICAL N/A 0 12-12 E-2' ' X100B ELECTRICAL N/A 0 12-12-84 E-3 X100C ELECTRICAL N/A 0 12-12-84 E-4 X100D ELECTRICAL- N/A 0 12-12 E-5 X100E ELECTRICAL N/A 0 12-14-84=

E-6 - X100F ELECIRICAL N/A 0 12-14-84 E-7 X100G ELECTRICAL N/A 0 12-14-84 E-8 X100H ELECfRICAL N/A 0 12-14-84 ,

E-9 X101A ELECTRICAL N/A 0 12-13 E-10' X101C ELECTRICAL N/A 0 12-13-84 E-11 X101D ELECTRICAL N/A -0 12-18-84 ,

E X101F ELECTRICAL N/A 0 12-18-84.

.E-13 X102A ELECTRICAL N/A 0 12-13-84 E-14 -X102B ELECTRICAL N/A 0 12-13-84

  • E-15 X102C ELECTRICAL N/A 0 12-14-84 E-16 X102E ELECTRICAL ~ N/A- 0 12-14-84 i cE-17 X102F ELECTRICAL N/A 0 12-14-84:
E-18 X012H ELECTRICAL' N/A 0 12-18-84 E X103A ELECTRICAL- N/A- 0. 13-84.

E-20' X103B ELECTRICAL N/A 0 12-16-84 E-21 X014A ELECTRICAL- N/A :0 12-13-84

. E-22 X104B ELECTRICAL N/A 0 12-13-84' E-23 X104C ELECTRICAL N/A 0 12-14-84 E X104E ELECTRICAL N/A 0 12-14-84 E-25 X104F ELECTRICAL N/A 0 12-16-84 12-18-84

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,E-26 X104G ELECTRICAL. N/A 0

'= .E-27 X105B ELdCTRICAL N/A 0 12-12-84.

E-28 X015C ELECTRICAL' N/A- 0 12-12 E-29 X015D ELECTRICAL N/A .0- 14-84

-E-30 X105E ELECTRICAL N/A 0 .12-13-84 E-31 X015G ELECTRICAL N/A 0 12-14-84 E-32 - X105H ELECTRICAL N/A 0 12-14-84 E-33 X015J ELECTRICAL N/A 0 12-18-84 E-34 X015K ELECTRICAL N/A 0 12-18-84

'E X2328 ELECTRICAL N/A 0 12-18-84 E-36 X232B ELECTRICAL N/A 0 12-18-84 H-2. PERSONAL LOCK TO DRYWELL LINER SEAL' N/A 0 01-19-85 i' M CAC-V5 INBOARD 0-RINGS N/A 0 12-31-84 M-3~ CAC-V6 INBOARD O-RINGS N/A 0 12-31-84 M-44 CAC-V7 INBOARD 0-RINGS N/A 0 02-21-85

' M-5 CAC-V9 INBOARD O-RINGS N/A 0 12-23-84 M-6 CAC-V16 INBOARD 0-RINGS N/A 0 12-26-84

, 'M-7' CAC-V17 INBOARD 0-RINGS N/A 0 03-14-85 821-2 B21-F010B 18 0 01-12-85 I~ (473 MAT /pgp)

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PENETRA- PREVIOUS TION LINE. TEST

- 4 TSIZE- RESULTS- s 1 TEST NO.  ?

EQUIPMENT TESTED (INCHES) (SCFH)- TEST DUE DATE 1B21-3 :321-F032A, E41-F006- 18 5.4 03-17-85 lB21-4: 'B21-F0328,'E51-F013, G31-F039 18 0.7 03-03 'CAC-1 CAC-V47 1 0 12-31-8A

+ .CAC-2 :CAC-V48 1 0.5 12-30-84

'.CAC-4 .CAC-V7,_V8, V22 20 5.4' 02-22 :CAC-51 CAC-V9,-V10,:V23 :18 2.3 12-23-84 CAC CAC-X20A,EV16- . 20 ~ 0.7- 12-26 ~

CAC-7: CAC-X208, V171 20 'O 12-26-84 CAC-9 -CAC-PV12005 -l' O 12-16-84

.CAC-10 CAC-PV1261; 1 0 12-16-84.

.CAC-11 -CAC-PV1227A1 1 0 12-14-84

< CAC ~CAC-PV1227B 1 0 12-14-84 CAC-14 .CAC-PV1227EL 1 0 12-15-84' CAC-15 CAC-FV1260 1 0 12-15- CAC-16 CAC-FV1231B 1 0- 12-14-84

'CAC-17 iCAC-PV3440~ 1.25 0 12-15-84:

'CAC-18. CAC-PV12250 1.25 0 12-15-84

-CAC-19 'CAC-PV12110 1 0 12-14-84 LCAC-20 -CAC-PV1262 1 0~ 12-14 ~ ^CAC-21 CAC-PV1208A 1 0 12-13-84 L :CAC-22. ~CAC-FV12098 1 0 12-13-84

.CAC-23: CAC-PV1205E 1 0 12-13-84

-CAC-241 CAC-PV1215E; 1 0 12-14-84

-CAC-25 CAC-PV12118 1.25 0 12-14-84 CAC-26 CAC-PV3439' 1.25 0 12-14-84

-CAC-27 CAC-PV3441 1.25 0 12-15-84 CAC-28' CAC-PV3442 1.~ 25 0 12-15-84

.CAC-29' CAC-PV3437- 1.25 0- 12-14 lCAC-30. CAC-PV3438 1.25 0 02-23 CAC-39 :CAC-PV1218C. 0.75- 0 12-16-84

-CAC-40 CAC-PV1219B 2.0 0 12-20-84 CAC-41' CAC-PV1225C 2.0- 0 12-18-84 CAC-42 CAC-PV1209D 1.0 0 12-18 E11-1 E11-F008, F009 20 5.2 03-10-85

/E11-2 .E11-F011A 4 0 03-28-85

~E11-31 E11-F011B 4 5.5 '12-30-84 -

)31 E11-4^ E11-F015A,' F017A '24 2.1 03-08-85' b cE11-5 E11-F0158, F017B 24- 0 01-24-85

.E11-6 E11-F016A, F021A- 14 0 03-26-85 E11-8 E11-F020A 24 13.5 03-29-85 E11 E11-F024A, F027A, F02dA 16 0 ,

02-02-85 E11-12 -E11-F024B, F0278, F028B 116 0 01-28-85 E11-13 E11-F025A- 0.75 0 02-04-85 E11 E11-F0258 0.75 0 01-17-85 E11 E11-F037D 0.75 0.1 12-22-84 '

E11-16 E11-F0378 0.75 0 12-16-84 E11-F043D 0.75 0.1 12-22-84

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MAXIMUM PENETRA- PREVIOUS

'$ TION LINE TEST-SIZE' RESULTS

-TEST NO. - EQUIPMENT TESTED (INCHES) (SCFH) TEST DUE DATE-

= E11-19 E11-F037C 0.75 0 12-16-84

.E11-20' . E11-F043C --0.75 0 12-16-84 E11 E11-F037A 0.75 0 12-16-84 Ell-23 E11-F097- '4 0 01-11-83 E11-24 E11-F007A 4 0 02-01-85

E11-25 .E11-F0078 4 0 01-28-85 E11-26' E11-F103A 1 0 02-02-85 l Ell-27 ~311-F103B 1 0 18-85 CAC-45 CAC-PV1219C 0.75 0 12-17-84

., E11-28' E11-F055A 4 0 02-04-85 E11-29. E11-F055B 4 0 01-05 E11-30' E11-V20 0.75 0 02-04-85 E11 B11-V21 0.75 0 01-05-85 E11-32 E11-F029 1 0 02-22-85

, E21-1 E21-F001A 14 3.6 02-21-85 E21-2 -E21-F001B 14 0.1 12-29-84 '

E21-3' E21-F004A,:F005A 10 0 02-18-85 E21-4 E21-F0048, F005B 10 0.1 12-23-84 E21-5 E21-F015A 10 0 02-21-85 E21-6 -- E21-F015B 10 0 12-29 ,

E21-7 E21-F031A 3 0 02-21 E21-8' E21-F0318 3 0 01-19-85 E41 E41-F002, F003 10 0 03-22-85 4' E41-2 E41-F012 4 0 12-19-84' E41-3 E41-F042 16 0 12-19-84 E41-4 E41-F022, F040~ 2 0 02-10-85 LE41-6 E41-F075, F079 2 0 12-19-841 E41-7_ E41-PV1218D, 12200 1 0 12-28-84 E41-8 E41-PV1219D, 1221D 1 0 02-18-85 E51-2 E51-F019 2- 0 .

12-17-84

E51-3 E51-F031 6 0 12-16 E51-4 E51-F002, F028 2 0 02-04-85 G16-1 G16-F003, F004 3 0 01-28-85 G16-2 G16-F019, F020 3 0.7 01-27-85 SA-1. SA-V448 1 0 02-23-85 SA-2 SA-V449- 1 0 03-23-85 LTIP-1 TIP-V1 3/8 0- 12-17-84

, TIP-2 TIP-V2 3/8 0 12-17-84

-TIP-3 TIP-V3 3/8 0 12-17-84 TIP TIP-V4 3/8 0 12-17-84 TIP-5 TIP N CHECK VALVE 3/8 0 12-17-84 TIP-6 TIP N SOLEN 0ID VALVE 3/8 0 12-17-84 (473 MAT /pgp)

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E Main Steam Isolation Valves B21-F022A,'F028A '24 0 03-18-85 821-F022B,~F0288 24 0 03-18-85

.B21-F022C, F028C- 24- 4.141 03-18-85 821-F022D, F028D 24 0 03-18-85

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