ML18038B448

Forwards Suppl Info Re Conformance w/NUREG-0737,Item II.E.4.2, Containment Isolation Dependability

ML18038B448
Person / Time
Site:	Browns Ferry
Issue date:	10/04/1995
From:	Salas P TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-2.E.4.2, TASK-TM TAC-M74615, TAC-M74616, NUDOCS 9510160083
Download: ML18038B448 (14)

Text

PRIORITY 1 (ACCELERATED RZDS PROCESSING) qREGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:9510160083 DOC;DATE: 95/10/04 NOTARIZED: NO FACIL:50-260 Browns Ferry Nuclear Power Station, Unit 2, Tennessee 50-296 Browns Ferry Nuclear Power Station, Unit 3, Tennessee AUTH.NAME AUTHOR AFFILIATION SALAS,P.

Tennessee Valley Authority RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)

SUBJECT:

Forwards suppl info re conformance w/NUREG-0737,Item II.E.4.2, "Containment Isolation Dependability."

DISTRIBUTION CODE:

A017D COPIES RECEIVED:LTR ENCL SIZE:

TITLE: OR Submittal:

Append J Containment Leak ate Testing NOTES DOCKET 05000260 P

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RECIPIENT ID CODE/NAME PD2-3 WILLIAMS,J.

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TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!

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Tennessee Valley Authority. Post Office Box 2000, Oecatur. Atabama 35609 OCT p4 1995 U.S. Nuclear Regulatory Commission ATTN:

Document Control Desk Washington, D.C.

20555 Gentlemen:

In the Matter of Tennessee Valley Authority Docket Nos.

50-260 50-296 BROWNS FERRY NUCLEAR PLANT (BFN)

UNITS 2 AND 3 SUPPLEMENTAL INFORMATION FOR CONFORMANCE WITH NUREG-0737~

ITEM II.E.4 2

AND 10 CFR 50'PPENDIX J (TAC NOS.

M74615 AND M74616)

This letter provides supplemental information regarding BFN Units 2 and 3 conformance with NUREG-0737, Item II.E.4.2, Containment Isolation Dependability, and 10 CFR 50, Appendix J, Primary Reactor Containment Leakage Testing.

This letter is specifically in response to the Staff's October 3,

1995 request for additional information to TVA.

As discussed in detail in the enclosure to this letter, the Auxiliary Boiler System piping was capped outside the primary containment.

The other capped portion of the line outside containment is leak tested as part of the Reactor Core Isolation Cooling piping boundary.

Thus, local leak rate test of the Auxiliary Boiler System is not required.

TVA has also verified that the containment isolation valves for the control air system are safety related.

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U.S. Kuclear Regulatory Commission Page 2

OCT 04 1995 There are no new commitments contained in this letter.

If you have any questions, please contact me at (205) 729-2636.

Sincerely, Pe

-.Salas Manager of Site Licensing cc (Enclosure):

Regional Administrator U.S. Nuclear Regulatory Commission Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 Mr. Mark S. Lesser, Acting Branch Chief U.S. Nuclear Regulatory Commission Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 NRC Resident Inspector Browns Ferry Nuclear Plant Route 12, Box 637

Athens, Alabama 35611 Mr. Z. F. Williams, Project Manager U.S. Nuclear Regulatory Commission One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852

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U.S. Nuclear Regulatory Commission Page 3

OCT 0c

>ssS SMK cc (Enclosure):

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P. Carier,,

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S'. Christenbury, ET 11H-K K. N. Harris, LP 3B-C R.

W. Huston, Rockville Office-C R.

D. Machon, PAB 1E-.BFN John P. Maciejewski, LP 3B-C T. J.

McGrath, LP 3B-C T.

W. Overlid, BR 4J-C E. Preston, POB 2C-BFN T.

D. Shriver, PAB 1A-BFN H. L. Williams, EDB 1A-BFN

RIMS, WT 3B-K

ENCLOSURE TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT (BFN)

UNITS 2 AND 3 SUPPLEMENTAL INFORMATION FOR CONFORMANCE WITH NUREG-0737'TEM II'D 4 '

AND 10 CFR 50@

APPENDIX i7 BACKGROUND On May 5, 1992 (Reference 1),

NRC requested information describing the differences in containment piping penetration design and testing between the three BFN units.

TVA initially responded by letter dated September 1,

1992 (Reference 2), by providing the anticipated containment isolation configuration at the time of the restart of Unit 3 and committed to notify NRC of any changes.

This preliminary information was the basis for the NRC's January 6,

1995 Safety Evaluation that addressed the differences between Units 2 and 3 (Reference 3).

TVA's August 3, 1995 letter (Reference

4) provided NRC with changes to the Unit 2 configuration that were performed subsequent to NRC review and corrections to the Unit 2 Safety Evaluation, dated March 22, 1991 (Reference 5).

Supplemental information was requested by NRC on October 3,

1995 (Reference 6).

SUPPLEMENTAL INFORMATION 1 ~

NRC REQUEST AUXILIARYBOILER SYSTEM TVA's August 3, 1995 letter states that the BFN Units 2

and 3 Auxiliary Boiler System has been modified to remove the containment penetration 210A check valves and install a cap and thus no longer requires local leak rate tests (LLRT).

Capped or flanged piping penetrations are subject to 10 CFR 50 Appendix J LLRTs unless the design and qualification of the penetration is such that the penetration no longer need be considered a penetration (i.e., permanently welded in a manner that conforms to standards of a containment repair).

A seal-welded cap or flange may qualify for an exemption, but is still considered a penetration.

Therefore, the staff requests that TVA clarify whether this cap meets the standards of a.

containment. repair.

If not, TVA should continue LLRT for this penetration until staff review and approval of an Appendix J exemption.

TVA RESPONSE Shown below is a sketch of the piping configuration after the modification to remove the Auxiliary Boiler tie to the Reactor Core Isolation Cooling (RCIC) system.

The Auxiliary Boiler line was cut and capped outside containment where it tied into the RCIC minimum flow bypass, line.

The remaining welded cap'ortion of the line is also located outside primary containment and is tested as part of the RCIC piping boundary..

Thus, local leak rate test of the Auxiliary Boiler System is not required and the welded cap in the containment boundary is leak tested as part of the RCIC system piping and valves.

7I-6 I2 Welded Cap RHR Piping to X-210A FCV-7]-34 Formerly to AuxiliaryBoiler 71-547 NRC REQUEST CONTROL AIR SYSTEM COMPRESSOR DRYWELL SUCTION BFN Units 2 and 3 are similar, but the information previously given the staff for Unit 2 was incorrect.

The fail-close isolation valves do not utilize spring force to close on loss of air or electrical power, but instead use an "integral air accumulator".

PAID 2-47E610-32-2 indicates that the operators on these valves utilize an air motor and that an accumulator air supply is provided for each valve.

This is an acceptable isolation arrangement assuming the accumulators and associated isolation valves are safety grade.

The staff requests that TVA verify and document the qualification of these components.

TVA RESPONSE TVA has verified that the primary containment isolation

valves, including the accumulators, for the control air system (Penetration 48 Valves 2-FCV-32-62, 2-FCV-32-63, 3-FCV-32-62, and 3-FCV-32-63), are safety related.

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.REFERENCES 1 ~

2.

3 ~

4 ~

.5.

NRC letter to TVA, dated May 5,

1992, Request for Additional Information to Review'rowns Ferry Nuclear Plant Units 1

and 3 Compliance with NUREG-0737 Item II.E.4.2 and 10 CFR 50, Appendix J TVA letter to NRC, dated September 1,

1992,

Response

to NRC Request for Additional Information Regarding Units 1 and 3

Conformance With NUREG-0737, Item II.E.4.2 and 10 CFR 50, Appendix J NRC letter to TVA, dated January 6,

1995, Browns Ferry Nuclear Plant Units 1 and 3 NUREG-0737, Item II.E.4.2, Containment Isolation Dependability TVA letter to NRC, dated, August 3, 1995, Units,2'nd 3

Supplemental Information for Conformance With NUREG-0737, Item II.E.4.2 and 10 CFR 50, Appendix J NRC letter to TVA, dated March 22,

1991, Issuance of Amendment and Compliance Review of 10 CFR 50, Appendix J and TMI Item II.E.4.2.1-4 6.

NRC letter to TVA, dated October 3,

1995, Request for Additional Information: Conformance With NUREG-0737 Item ZI.E.4.2 and 10 CFR 50, Appendix J E-3

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