ML20086H669

Responds to NRC Safety Evaluation on Conformance of Plants to Station Blackout Rule (10CFR50.63).Safety-related Batteries 2 & 3 Will Be Replaced W/Batteries Having Higher Number of Plates Per Cell

ML20086H669
Person / Time
Site:	Browns Ferry
Issue date:	12/02/1991
From:	Zeringue O TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9112090287
Download: ML20086H669 (11)

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December 2, 1991 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 Gentlemen:

In the Matter of ) Docket Nos. 50-259 Tennessee Valley Authority ) 50-296 BROWNS FERRY NUCLEAR PhANT (BFN) - RESPONSE TO NRC SAFETY EVALUATION (SE)

ON THE CONFORMANCE OF BFN PLANT WITil THE STATION BLACEOUT RULE (SBO)

(10 CFR50.63)

Reference:

1. TVA letter dated August 13, 199;, Response to NRC Safety Evaluation (SE) on the Conformance of BFN Plant with the Station Blackout Rule (SBO) (10 CFR50.63) ..

2. NRC letter to TVA dated July 11, 1991, Safety Evaluation on the Conformance of BFN with the Mation Blackout Rule (TAC Nos. 68517, 68518, and 68519)

This letter providea TVA's response to Reference 2, which transmitted the SE regarding BFN's compliance to the SB0 Rule. In Reference 2, the NRC staff concluded that BFN Units 1 and 3 are not in conf ort;ance with the SB0 Rule. The NRC requested that TVA submit a revised response for Unit 3 no later than December 31, 1991, and for Unit 1, no later than 24

~

months before the scheduled restart date. TVA's response for Unit 2 was provided in Reference 1.

Enclosure 1 contains TVA's response to each of the staff's recommen-dations for Unit 3 and for Unit 1. where possible. TVA vill submit a revised response for Unit 1 on a schedule that meets HRC's requested time frames. A summary list of commitments contained in this letter is provided in Enclosure 2. TVA requests the NRC review and confirm BFN's conformance to 10 CFR50.63 based en this response and the fullfillment of -

commitments provided. /(i

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'U.S. Nuclear Regulatory Commission December 2, 1991 If you have any questions, please telephone J. E. McCarthy, Restart Licensing Manager, at (205) 729-2703, i

l Sincerely,

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,- s 5I O' J Zering e ]

t Enclosures cc (Enclosures):

NRC Resident Inspector Browns Ferry Nuclear Plant Route 12, Box 637 Athens, Alabama 35609-2000 Mr. Thierry M. Ross, Project Manager U.S, Nuclear Regulatory Commission One White Flint,-North 11555 Rockville Pike Rockville, Maryland 20852 Mr. B. A. Wilson, Project Chief

-U.S. Nuclear Regulatory Commission Region II 101_Marietta Street, NV, Suite 2900 Atlanta, Georgia 30323 l-

1 -- -. 2 U.S. Nuclear Regulatory Commission V

• December 2,1991 RRB:JEM:EBS:DKF-cc: RIMS, MR 2F-C (Enclosures)

R. R. Baron, PAB-lC-BFN (Enclosures)

M. J. Burzynski, LP SB-C (Enclosures)

M. L. Butler, LP 6A-C J. R. Bynum, LP 3B-C E. S. - Christenbury, ET 11H-F. (Enclosures)

W. R. Cobean, Jr., LP 3B-C (Enclosures)

L. M. Cuoco, LP 5B-C (Enclosures)

M. J. Fecht, LP 5B-C K. G.-Hess, ATH 3-BFN R. W. Huston, Rockville Licensing Office (Enclosures)

H. F. McCluskey, MOD 2A-BFN T. J. McGrath, LP 3B-C (Enclosures)

G. R. Mullee, BR SD-C D. E. Nunn, LP 3B-C (Enclosures)

C. M. Root, PAB IC-B~rN (Enclosures)

J. R. Rupert, EDB 1A-BFN (Enclosures)

J. A. Scalice, POB 2C-BFN G. G. Turner, PSB 1K-BFN PLLIC440/95 2

! + .

' Page 1 ot 3 ENCLOSURE 1 RESPONSE TO NRC' S SATETY EV ALUATION ON CONFORMANCE OF THE BFN PLANT WITH THE SB0 RULE The following provides TVA's response to the NRC's Safety Evaluation (SE) recommendations contained in the enclosure to their July 11, 1991 letter SE Item _2,1 RecommendaMops_ Lor _Unitsl_2nand_3:

" Verify and confirm that an SBO on all 3-units envelopes (particularly with respect to station bettery capacity adequacy) each ein-19 and double unit Sno combination (assuming a loss of offsite power on all thcee units)."

TVA's Respop_se The response provided in Reference 1 app 1ted to Units 1, 2, and 3.

Reference 1 confirmed that TVA*e evaluation envelopes the single and double unit SB0 combinations that could occur.

SE Ites42.2 Recommendations _ for Un(ts_LandJ "In order for thi plant to conform to the SBO rule for Units 1 and 3, the licensee should describe the modifications that will be required to the DC power supply systems and/or the DC connected loads to assure adequate battery capacity for a 4-hour SB0 event. The licensee should repeat battery calculations (if necessary) using conservative assumptions, and confirm tL.-.

the battery capacity is adequate for an SBO event of four hours. The licensee should verify the adequacy of the DC power supply for the turbine bearing oil pump, the generator emergency seal oil pump, and for the control and field flashing of the EDCs during an SBO."

TVA's Response Based on preliminary evaluations, TVA has identified modifications to the DC Power Supply System and DC connected loads for Units 1, 2, and 3 necessary to assure adequate battery capacity for a 4-hour SB0 event during multi-unit operation. The BFN SBO P.alti-unit calculation and the DC distribution system-single line drawings for their respective units were used as the basis for determining the required modifications.

Safety-related Unit batteries 2 and 3 will be replaced with batteriep h="ing a higher number of plates per cell and containing greater ampere naur capacity.

The existing Unit Preferred Motor-Motor-Generator (MMG) sets, which constitute the largest continuous connected load to the safety-related batterien, will either be transferred .o a non safety-related battery or load shed during an SBO. The 120V AC Reactor Core Isolation Cooling (RCIC) system controls, which are currently supplied from the KMG sets, will be transferred to an appropriate source. The BFN SBO Multi-unit calculation and an electrical system study confirn that battery capacity will be adequate for an SBO event of 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> considering these modifications. The load tabulations compiled for the Multi-unit calculation were based on field verified Unit 2 loads and the assumption that loads on Units 1 and 3 were equivalent, since field verified load data will not be available until walkdowns are completed. The calculation details a worse case credible event sequence developed from a review of the FSAR, detailed discussions with operations, and a review of l

Page 2 of 3 accident /SBO procedures. This calculation and the electrical system study ,

conservatively demonstrate adequate battery capacity.

The Multi-unit calculation will be revised using field verified walkdown data ,

for Units.2 and 3 by March 31, 1992.

This SE recommendation also states that TVA should verify the adequacy of the

- DC power supply for the turbine bearing oil pump, the generator emergency seal oil pump, and for the control and field flashing of the Emergency Diesel Generators (EDGs) during an SBO. TVA's SBO evaluation takes no credit for

- this equipment. Thus, in relation to SBO, there is no need to verify the-adequacy of the DC power supply to this equipment.

HE. Item 2. h4 Recommendajigits-for Uni _tu 1 an U t "The recommendations described above for Unit 2 apply for Units 1 and 3 as well, and the licensee's subsequent responses for Units 1 and 3.must address

- these items." (Revise heat-up calculations for the control room, safety-related equipment rooms and the drywell using more conservative values. )

TVA's Respones In Reference 1 TVA committed to evaluate the recommended input data (i.e.,

initial-RCIC/HPCI room temperature, drywell leakage rate, heat load per person),--and. utilize it in the associated calculations, as applicable, for Unit 2. Input data, consistent with that used in the Unit 2 calculations, will be used in the calculations.for Units 1 and 3. The calculations for Units 1 and 3 will be completed by March 31, 1992.

SE Iten 2.2.5 Recommendations A t_, Units _1 apd 3:

"The recommendations described above for Unit 2 apply for Units 1 and 3 as

- well, and the licensee's subsequent' responses for Unite 1 and 3 must address these items." (The licenses should reevaluate the Containment Isolation Valves according to the-exclusion criteria in Regulatory Guide (RC) 1.155.

The licensee should listf in appropriate procedures the CIVe which are normally-open or normally-closed and fail as-is upon loss of AC power, and

- cannot-be excluded'by the criteria given=-in RG 1.155, and identify the actions-  ;

- necessary to ensure tha' these valves are fully closed, if necessary. The staf f's position is val e closure needs to be confirmed by position indication -

4 (local, mechanical, remote, process information, etc.).]

TVA's Response TVA will confirm that containment isolation valves (CIV) for Units 1 and 3 were evaluated in accordance with the exclusion criteria-of Regulatory Guide:

(RG) 1.155 or re-evaluate the containment isolation valves (CIV) for Unita 1

- and 3 in accordance with the exclusion criteria by March 31, 1992. TVA will-list in appropriate procedures those CIVs that are normally-closed or normally-open. and f ail-as-is upon loss of AC power, and can not be excluded by the criteria given in RG 1.155. TVA will identify actions necessary to ensure these valves are fully closed, if necessary. The appropriate procedures will be revised prior to the restart of each unit.

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page 3 of 3 ET l e.m_2M _gecommendation_fp_r_ Units 1 and) :

"The licensee should confirm and document the necessary modifications required to ensure suffielent class IE battery capacity for all three units. This documentation should be included in other documentation to be maintained in support of the SBO submittals."

UA's Responsen See TVA's response to SE Item 2.2.2.

SE_Ites_2.5 Recommendationsj g_r_U_ nits 1 and 3:

"The recommendations described above for Unit 2 apply for Units 1 and 3 as well, and the licensee's subsaquent responses for Units 1 and 3 must address these items." (The licensee should verify that SBO equipment is covered by an appropriate QA program consistent with the guidance of RG 1.155.)

T XVa_R eipon s e_ :

SBO equipment for Units 1 and 3 is covered by an appropriate QA program consistent with the guidance of RG 1.155. The response provided in Reference 1 applies to the three Browns Ferry units.

SE U;em 2.6 Recommeydations for Units I and 3:

"The recommendations described above for Unit 2 tpply for Unita 1 and 3 as well, and the licensee's subsequent responses for Units 1 and 3 must address these items." (The licensee should implement an EDG reliability program which meets the guidance of RG 1.155, Section 1.2. If an EDG reliability program currently exists, the program should be evaluated and adjusted in accordance with PG 1.155. Confirmation that such a program is in place or will be implemented should be included in the documentation supporting the 5B0 submittale that is to be maintained by the licensee.)

TVA's Response:

The EDG Reliability Program at Browns Ferry meets the guidance of RG 1.155, Section 2. The response provided in Reference 1 for Unit 2 applies to the three Browns ferry units.

l i

a ENg10SURE 2

SUMMARY

LISLQLqotO{LIMEliTS

1. TVA will implement modifications to the Dc Power Supply System and DC connected loads as described in TVA's response to the SF Item 2.2.2 Recommendations (See F.nclosure 1).

2. The BFN SBO Multi-unit calculation will be revised using field verified j walkdown data for Unita 2 and 3 by March 31, 1992.

3. Heat-up calculations for Unita 1 and 3, using input data consistent with that used in the Unit 2 calculations, will be completed by March 31, 1992.

4. TVA will evaluate containment isolation valven (CIV) for Unita 1 and 3 in accordance with the exclusion criteria of RG 1.155 by March 31, 1992.

5. Unita 1 and 3 CIVe that can not be excluded will be included in appropriate proceduren prior to restart of each unit.

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i. LICENSING TRANSMITTAL TO NRC .l

SUMMARY

AND CONCURRENCE SHEET THE PUPPOSE OF THIS CONCURRENCE SHEET IS TO ASSURE THE ACCURACY AND -

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COMPLETENESS OF TVA SUBMITTALS TO THE NRC.

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-DATE-Il/P/9l DATE DUE NRC -// //5/9/ p DATE DUE NRC SUBMITTAL PREPAPED BY (1) hdSkgbbn 3 ACTION NO.

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'A concurrence signature reflects that the signatory has assured that the submittal is appropriate and consistent with TVA Policy, applicable commitments are approved for implementation, and supporting documentation for submittal completeness and accuracy has be9n prepared.

CONCURRENCE (3)

,JAME OJ_G6HIZATION ._ .11GNATURE DATE J. A. Scalice P13nt Mangner t I! b/

R. R. Baron Site Licensinz Y4 h.__ // 4 /

NT E. F. McCluskey VP. Restart Operat4c? g h I / / // ?/' /

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J. R. Rupert Nuclear Enz.

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E. G. Wallace Mgr.. NL&RA ANac //[fNI APPROVED DATE NLRA MANAGER PLLIC440/6

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COMPLETENESS OF TVA SUBMITTALS TO THE NRC. 6 "C' cl& ls /Zhi/9/ #

ORIGINAL *fA46ET p EXTENDED DATE ll/P/4l DATE DUE NRC ////5/91 DATE DUE NRC SUBMITTAL PREPARED BY (1) kcl 35:p[eIm ACTION NO.

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INDEPENDENT REVIEW (2) C CD C DATE II E l

-A concurrence signature reflects that the signatory has assured that the submittal is appropriate and consistent with TVA Policy, applicable commitments are approved for implementation, and supporting documentat.on for submittal completeness and accuracy has been prepared.

rgpe, / J P CONCURRENCE (3)

NAME ORGANIZATION 4I33ATURE DATE Plant Ma.nazer / D // 7 '

J. A. S c a_.li c e '

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R. R. Bar>n Site Licensinz i _ H. F. McCluskey VP. Restart Operations

[J. R. Rup,_grt Nuclear Eig'..

VC. G. Creamer Restart Enzineering I .E G. Wallace Mgr. NL&RA APPROVED DATE NLRA KANAGER PLLIC440/6

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LICENSING TRANSMITTAL TO NRC ,

. . dUMMARY AND CONCURRENCE SHEET THE PURPOSE OF THIS CONCURRENCE SHEET IS TO ASSURE fHE ACCURACY AND

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COMPLETENESS OF TVA SUBMITTALS TO THE NRC. K'r d.h. n /zhi/9/

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• submittal completeness and accuracy has been prepared.

CONCURRENCE (3)

NAME ORGANI2ATION SIGNATURE DATE

.J. A. Scalice Plant Manager

l. R. Baron Site Licensinz H. F. McCluskey VP. Restart Operations J. R. Rupert Nuclear Enr. /1 e f _

C. G. Creamer Restart Ennineerine Ac<W //!/L/f/

E. G. Wallace Mnr. NL&RA APPROVED DATE NLRA MANAGER PLLIC440/6

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INDEFENDEIC REVIEW (2) DATE A concurrence oignature reflects that the signatory has assured that the submittal is appropriate and consistent with TVA Policy, applicable ce=: nit =ents arc approved for impicmentation, and supporting documentation for submittal completeness and accuracy has been prepared.

CONCUF2ENCE (3)

SIGMPE

_EAS -

ORCANIZATJ0F _JATJ L L 1cJL11ce Plant _Manarer

,J._.R., _BjlLt.on Site LicAnlinz H. T. McCluskev VL Rest,altAgrAtiens t i E.,_Rupert Nuclear Enr.

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APPROVED DATE -

RLRA MARAGER PLLIC440/6

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