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{{#Wiki_filter:REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)ACCE.S5lON NBR:8410110067 OC DATE: 84/10/01 NOTARI D: YES FACIL:50-259 Browns Ferry Nuclear Power Stationi Unit li Tennessee 50-260 Browns Ferry Nuclear Power Stations Unit 2<Tennessee 50-296 Browns Ferry Nuclear Power'Stations Unit 3<Tennessee AUTH.NAME AUTHOR AFFILIATION MILLS g L,M>>Tennessee Valley Authority RECIP~NAME RECIPIENT AFFILIATION DENTONgH~RE Office of Nuclear Reactor Regulationi Director DOCKET 05000259 05000260 05000296
{{#Wiki_filter:REGULATORY INFORMATION DISTRIBUTION SYSTEM                             (RIDS)
ACCE.S5lON NBR:8410110067                                 OC DATE: 84/10/01   NOTARI   D: YES     DOCKET FACIL:50-259 Browns Ferry Nuclear Power Stationi Unit li Tennessee                                 05000259 50-260 Browns Ferry Nuclear Power Stations Unit 2< Tennessee                               05000260 50-296 Browns Ferry Nuclear Power 'Stations Unit 3< Tennessee                               05000296 AUTH. NAME           AUTHOR AFFILIATION MILLS L,M>>
g              Tennessee Valley Authority RECIP NAME
          ~             RECIPIENT AFFILIATION DENTONgH ~ RE         Office of Nuclear Reactor Regulationi Director


==SUBJECT:==
==SUBJECT:==
Responds to 800210 request for addi info re proposed inser vice pump 8 valve testing program.Revised program encl/including requests for relief from certain ASME requirements, Program supersedes 820831 program, DISTRIBUTION CODE: A047D COPIES RECEIVED:LTR ENCL SIZE;TITLE."OR Submittal:
Responds   to 800210 request for addi info re proposed inser vice pump 8 valve testing program. Revised program encl/
Inservice Inspection/Testing NOTES:NMSS/FCAF 1cy.1cy NMSS/FCAF/PM'L:06/26/73 NMSS/FCAF 1cy, 1cy NMSS/FCAF/PM'L:06/28/7q NMSS/FCAF 1cy.1cy NMSS/FCAF/PM'Lo07/0?/76 05000?59 05000260 05000296 RECIPIENT ID CODE/NAME NRR ORB2 BC 01 COPIES LTTR ENCL 7 7 RECIPIENT ID CODE/NAME COPIES LTTR ENCL INTERNAL: ADM/LFMB NRR/DE/MEB 15 NRR/DL/TAPMG RGN2 1 0 ELD/HDSO 1 1 gg/MTEB 14 1 1 rRE'G FIL 04 1 1 EXTERNAL: ACRS NRC PDR NTIS NOTES;16 10 10 02 1 1 1 1 LPDR NSIC 03 05 TOTAL NUMBER OF COPIES REQUIRED!LTTR 30 ENCL 28 4~1 E li lp ll ll'I 4 k h il  
including requests for relief from certain ASME requirements, Program supersedes 820831 program, DISTRIBUTION CODE: A047D                   COPIES RECEIVED:LTR                 ENCL       SIZE; TITLE."OR Submittal: Inservice Inspection/Testing NOTES:NMSS/FCAF     1cy. 1cy                                                                       05000?59 NMSS/FCAF/PM'L:06/26/73 NMSS/FCAF   1cy, 1cy                                                                       05000260 NMSS/FCAF/PM'L:06/28/7q NMSS/FCAF   1cy. 1cy                                                                       05000296 NMSS/FCAF/PM'Lo07/0?/76 RECIPIENT                     COPIES                    RECIPIENT          COPIES ID CODE/NAME                   LTTR ENCL                 ID CODE/NAME       LTTR ENCL NRR ORB2 BC    01                            7    7 INTERNAL: ADM/LFMB                                         1    0    ELD/HDSO NRR/DE/MEB     15                             1   1     gg/     MTEB   14 NRR/DL/TAPMG                                  1   1   rRE'G FIL         04 RGN2                                          1   1 EXTERNAL: ACRS             16                           10   10     LPDR            03 NRC  PDR      02                             1   1     NSIC            05 NTIS                                          1   1 NOTES; TOTAL NUMBER OF COPIES       REQUIRED! LTTR                         30   ENCL     28
;-0~TENNESSEE VALLEY AUTHORITY cHATTANooGA.
 
TENNEssEE 37401 400,Chestnut
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'Street"Tower II October 1, 1984 Mr.Harold R.Denton, Director Office of Nuclear Reactor Regulation U.S.Nuclear Regulatory Commission Washington, D.C.20555  
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TENNESSEE VALLEY AUTHORITY cHATTANooGA. TENNEssEE 37401 400,Chestnut 'Street"Tower       II October 1, 1984 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555


==Dear Denton:==
==Dear Denton:==
In the Matter of the Tennessee Valley Authority Docket Nos.50-259 50-260 50-296 By my letter to you dated August 31, 1982, we submitted for your staff's review the proposed Inservice Pump and Valve Testing Program for the Browns Ferry Nuclear Plant units 1, 2, and 3.In response to your staff's request;, additional information was submitted by my letter to you dated April 6, 1983.I A request for additional information was transmitted to TVA by letter from D.B.Vassallo to H.G.Parris dated February 10, 1984.In response to that request, we have revised the program provided as enclosure 1.Included are requests for relief from certain Code requirements.
None of the changes reflect a relaxation of test procedures.
Specific responses to each of the requests made in the February 10, 1984 letter is provided in enclosure 2.The revised Inservice Pump and Valve Testing Program for Browns Ferry provided as enclosure 1, supersedes the program submitted by my letter to you dated August 31, 1982.If you have any questions, please get in touch with us through the Browns Ferry Project Manager.Very truly yours, d Sworn to.ng subscribe me th s'M day of TENNESSEE VALLEY AUTHORITY c L.M.Mills, Manager Nuclear Licensing befo e 1984.Notar y Public My Commission Expires Enclosures cc: See page 284iOii0067 84100i"PDR ADOCK 05000259 P PDR An Equal Opportunity Employer l 9'I~k'y('~'I'g g'$P lt t', 1*I F F"'~~.'P C f'h I JI S y I I'ae F h 4 r-1 4~A N ll h 0 II V L-~p l Mr.Harold R.Denton October 1, 1984 cc (Enclosures):
U.S.Nuclear Regulatory Commission Region II ATTN: James P.O'Reilly, Regional Administrator 101 Marietta Street, Suite 2900 Atlanta, Georgia 30323 Mr.R.J.Clark Browns Ferry Project Manager U.S.Nuclear Regulatory Commission 7920 Norfolk Avenue Bethesda, Maryland 20814 Mr.E.H.Girard U.S.Nuclear Regulatory Commission Region II 101 Marietta Street, Suite 2900 Atlanta, Georgia 30323 1
ENCLOSURE 1 ASME SECTION XI INSERVICE PUMP AND VALVE TESTING PROGRAM BROMNS FERRY NUCLEAR PLANT UNITS 1, 2, AND 3 (DOCKET NOS.50-259,-260,-296)Attachment 1: Inservice Testing Program for ASME Code Classes 1, 2, and 3 Pumps Attachment 2: Valves to be Cycled for ASME Section XI (IWV-3410, 3510, 3520, and 3610)Attachment 3: Category A Valves and Testing Criteria (Appendix J, Secti'on XI, or both)Attachment 4: Requests for Relief 1~AXiKP29K 1 ItJSERVICE leSTIN'i PKCP~uk FOR AS c.CODE CLASSES 1, 2, AtJD 3 PU."'PS The following table provide" a tabulation of pmps that testing requirements of Sub"ecticn IMP of Section XI of Pressur": Vessel Code, 1980 Edi'icn, and Add nda thrcugh p.ograrn will be applicable until August 31, 1992.are subjec'c t'.e the I~YZ J.'w ler and Hinter 19tC.Thi s This tabulation identifies the pcnps to be tes'ed, pup code classes, pararne'ers to be rneasur ed, and test irtervals.
HPCI.RCIC Core Spray Standby Liquid Control RFIRS''(1)2 NR Q 0 Q 2 Q Q Q 0 2 Q 0 Q 0 JJR Q Q Q'2 2 lJR JR Q Q 3 tJR Q Q Q H~Ma~3 Zi Z tJA tJA 0 0<Q JJR'JA Q tJA'!JR J~n tJA 0 NR tJA~0 0 H Rotative Speed Lor P Lubricant Level or Pressur" P'ifferential Pressr:r e tJR tarot Required Pi Inlet Pres ure tJA tJo Avail able Qi Flow Rate H Mcntrg y Tb Bearir:g Temperature Q Quarterly V Vibraticrr Anrpl i tude A Annually (1)These punps are ir a systerr ccexnon to units 1, 2, and 3.Ability to start the pumps will be derncnstrated frcrn each control roan, but canparison to baseline parameters of vibraticn, flew rate, and differential pressure will be perfcrrned for instrumentation in unit 3 only, for ccnsistency of d'ata.


4~The following table provides a listing of systems, valve numbers, types, categories, test frequencies, and type of tests for those valves to be I cycled in accordance with ASME Section XI, IHV-3410, 3510, 3520, and 3610.4 Main Steam Main Steam (Rel'ief Valves)Feedwater (Check Valves)XLQD'.1-14 1-15 1-26 1-27 1-37 1-38 1-51 1-52 1-4 1-5 1-18 1-19 1-22 1-23 1-30 1-31 1-34 1-41 1-42 1-179 1-180 3-554 3-558 3-568 3-572 23-34 23-40 23-46 23-52 23-57 (U-142)A A A A A A A A C C C C C C C C C C C C C AC AC AC AC TEST HKQXH<Y Q Q Q Q Q Q Q Q 60 months 60 months 60 months 60 months 60 months 60 months 60 months 60 months 60 months 60 months 60 months 60 months 60 months Operating Cycle Operating Cycle Operating Cycle Operating Cycle Full Cycle Full Cycle Full Cycle Full Cycle Full Cycle Full Cycle Full Cycle Full Cycle Meets IWV-3510 Meets IWV-3510 Meets'IWV-3510 Meets IWV-3510 Meets IWV-3510 Meets IWV-3510 Meets IWV-3510 Meets IWV-3510 Meets IWV-3510 Meets IWV-3510 Meets IWV-3510 Meets Mf-3510 Meets IWV-3510 Full Cycle, PV-8 Full Cycle, PV-8 Full Cycle, PV-8 Full Cycle, PV-8 Full Cycle-Full Cycle Full Cycle Full Cycle Full Cycle RHRSW ,(Check Valves)23-502 23-506 23-522 23-526 23-542 23-546 23-561 23-565 23-579 23-580 23-581 23-582 23-591 23-594 23-597 23-588 C C C C C C C C (510 U1)C (530 U1)C (550 U1)C (569 U1)C C C C C Q Q Q Q Q Q Q Q Q Q Q Q Q Q Q Q Full Cycle Full, Cycle Full Cycle Full Cycle Full Cycle Full Cycle Full Cycle Full Cycle Full Cycle Full Cycle Full Cycle Full Cycle Full Cycle-Full Cycle Full Cycle Full Cycle
In the Matter of the                                        Docket Nos. 50-259 Tennessee      Valley Authority                                        50-260 50-296 By my    letter to you dated August 31, 1982, we submitted for your staff's review the proposed Inservice Pump and Valve Testing Program for the Browns Ferry Nuclear Plant units 1, 2, and 3. In response to your staff's request;, additional information was submitted by my letter to you dated    April 6,     1983.
~Y~gM SLC (Check Valves)63-514 63-516 63-525 63-526 MCXKQBX C C AC AC TEST GKQUKKX Q Q Operating Cycle Operating Cycle P OF Full Cycle Full Cycle Full Cycle, Full Cycle, PV-8 PV-8 SLC (Relief Valves)SLC (Explosive Valves)EE%63-512 63-513 63-SA 63-SB 67-13 67-14 67-17 67-18 67-21 67-22 67-25 67-26 67-48 67-49 2-year 2-year Cycle Cycle Operating Cycle Operating Cycle Tech Spec 4.4.A.2 Tech Spec 4.4.A.2 IWV-3610 1WV-3610 Full Cycle Full.Cycle Full Cycle Full Cycle Full Cycle Full Cycle Full Cycle Full Cycle Full Cycle Full Cycle EEL (Check Valves)67-502 67-582 67-622 67-619 67-541 67-542 67-584 67-585 67-648 67-649 67-656 67-657 67-559 67>>558 67-638 67<39 67-600 67-601 67-659 67-660 67-556 67-598 67693 (U-3)67-694 (U-3)67%95 (U-3)67-696 (U-3)67-705 (U-3)67-706 (U-3)67-703 (U-3)67-704 (U-3)C C C C C C C C C C C Q Q Q Q Q Q Q Q Q Q Q Q Q Q Q Q Q Q Q Q Q Q Q Q Q Q Q Q Q Q Part Cycle, Part Cycle, Part Cycle, Part Cycle, Part Cycle, Part Cycle, Part Cycle, Part Cycle, Part Cycle, Part Cycle, Part Cycle, Part Cycle, Part Cycle, Part Cycle, Part Cycle, Part Cycle, Part Cycle, Part Cycle, Part Cycle, Part Cycle, Part Cycle, Part Cycle, Part Cycle, Part Cycle, Part Cycle, Part Cycle, Part Cycle, Part Cycle, Part Cycle, Part Cycle, PV-,10 PV-10 PV-10 PV-10 PV-10 PV-.10 PV-10 PV-10 PV-10 PV-10 PV-10 PV-10 PV-10 PV-10 PV-10 PV-10 PV-10 PV-10 PV-10 PV-10 PV-10 PV-10 PV-10 PV-10 PV-10 PV-10 PV-10 PV-10 PV-10 PV-10
I A  request for additional information was transmitted to TVA by letter from D. B. Vassallo to H. G. Parris dated February 10, 1984. In response to that request, we have revised the program provided as enclosure 1.
Included are requests for relief from certain Code requirements. None of the changes reflect a relaxation of test procedures. Specific responses to each of the requests made in the February 10, 1984 letter is provided in enclosure 2.
The    revised Inservice Pump and Valve Testing Program for Browns Ferry provided as enclosure 1, supersedes the program submitted by my letter to you dated August 31, 1982.
If you      have any questions,   please get in touch with us through the Browns Ferry Project Manager.
Very  truly yours, TENNESSEE VALLEY AUTHORITY c
d L. M. Mills, Manager Nuclear Licensing Sworn    to  .ng subscribe    befo  e me  th  s    'M  day  of                1984.
Notar y Public My Commission Expires Enclosures cc: See page        2 84iOii0067 84100i


EECM (Check Valves-Continued) 67-528 (U-1)67-529 (U-1)67%34 (U-1)67%35 (U-1)67-521 (U-1)67-522 (U-1)67-630 (U-1)67-631 (U-1)67-624 (U>>1)67-625 (U-1)67-514 (U-1)67-515 (U-1)67-627 (U-1)67-628 (U-1)67-507 (U-1)67-508 (U-1)67-838 67-839 67-843 67-844 KQBX C C C C C C C C C C C C C C C C C C C C TEST ZEK8LKKX Q Q Q Q Q Q Q Q Q Q Q Q Q Q Q Q Q Q Q Q Part Cycle, Part Cycle, Part Cycle, Part Cycle, Part Cycle, Part Cycle, Part Cycle, Part Cycle, Part Cycle, Part Cycle, ,Part Cycle, Part Cycle, Part Cycle, Part Cycle, PV-10 PV-10 PV-10 PV-10 PV-10 PV-10 PV-10 PV-10 PV-10 PV-10 PV-10 PV-10 PV-10 PV-10 Part Cycle, PV-10 Part Cycle, PV-10 Part Cycle, PV-10 Part Cycle, PV-10 Part Cycle,.PV-10 Part Cycle, PV-10 67-715 (U-3)67-716 (U-3)67-713 (U-3)67-714 (U-3)67-723 (U-3)67-724 (U-3)67-725 (U-3)67-726 (U-3)67-737 (U-,3)67-738 (U-3)67-735 (U-3)67-736 (U-3)Q Q Q Q Q Q Q Q Q Q Q Q Part Cycle, Part Cycle, Part Cycle, Part Cycle, Part Cycle, Part Cycle, Part Cycle, Part Cycle, Part Cycle, Part Cycle, Part Cycle, Part Cycle, PV-10 PV-10 PV-10 PV-10 PV-10 PV-10 PV-10 PV-10 PV-10 PV-10 PV-10 PV-10 Recirculation Loops 68-3 68-79 TEST~CKBX HMlKhLCX Cold Shutdown Cold Shutdown Full Cycle Full Cycle Recirculation Loops (Check Valves)68-508 68-523 68-550 68-555 AC AC AC AC Operating Cycle Operating Cycle Operating Cycle Operating Cycle Full Full Full Full Cycle, Cycle, Cycle, Cycle, PV-8 PV-8 PV-8 PV-8 RWCU RWCU (Check Valves)RCIC 69-1 69-2 69-579 69-624 71-2 71-3 71-5 71-6A ,71-6B 71-34 71-8 71-9 71-10 71-17 71-18 71-25 71-37 71-39 71-40 71-22 (U-3)-AC AC A A B B B B B B B B B B B A AC B Operating Cycle Operating Cycle Cold Shutdown Cold Shutdown Q Q Q Q Q Q Q Q Q Q Cold Shutdown Cold Shutdown Cold Shutdown Q Full Full Full Full Cycle Cycle Cycle, Cycle, Full Cycle Full Cycle Full Cycle Full Cycle Full Cycle Full Cycle Full Cycle Full Cycle Full Cycle Full Cycle Full Cycle Full Cycle Full Cycle Full Cycle Full Cycle Full Cycle PV-8 PV-8 RCIC (Check Valves)RCIC (Relief Valves)HPCI 71-580 71-597 71-598 71-599 71-600 71-508 71-592 71-543 71-503 73-81 73-2 73-3 73-5 AC Q C Q C Q C Q C Q C Operating Cycle AC Q 60 Months 60 months Cold Shutdown Cold Shutdown Cold Shutdown Q Full Full Full Full Full Cycle Cycle, Cycle, Cycle, Cycle, PV-11 PV-11 PV-11 PV-11 Full Cycle Full Cycle Full Cycle Full Cycle Internal Inspection, PV-9 Full Cycle, PV-11 Meets IWV-3510 Meets IWV-3510 TEST MCZKEK ZlKQL~~Y HPCI~(Continued)
"PDR ADOCK          05000259 P                        PDR An Equal Opportunity Employer
HPCI (Relief Valves)HPCI (Check Valves)RHR 73-6A 73-6B 73-16 73-18 73-19 73-26 73-27 73-34 73-43 73 44'73-45 73-30 73-574 73-506 73-559 73-517 73-603 73-609 73-633 73-634 73-635 73-636 74-1 74-2 74-7 74-12 74-13 74-24 74-25 74-30 74-35 74-36 74 47 74-48 74-52 74-53 74 54 74-57 74-58 74-59 74-60 74-61 74-66 74-67 74-68 B B B B B B B B B A AC B C C AC AC C C C C B B B B B B B B B B A A B A AC A A B A A B A AC Q Q Q Q Q Q Q Cold Shutdown Q Cold Shutdown Cold Shutdown Q 60 Months 60 Months Q Operating Cycle Q Q Q Q Q Q Q Q Q Q Q Q Q Q Q Q Cold Shutdown Cold Shutdown Q Cold Shutdown Cold Shutdown Q Q Q Q Q.'Q Cold Shutdown Cold Shutdown Full Cycle Full Cycle Full Cycle Full Cycle Full Cycle Full Cycle Full Cycle Full Cycle Full Cycle Full Cycle Full Cycle Full Cycle Meets IHV-3510 Meets IHV-3510 Cycle Cycle Cycle, Cycle, Cycle, Cycle, Full Full Full Full Full Full Full Full Full Full Full Full Full Full Full Full Full Full Full Full Full Full Full Full Full Full Full Full Full PV-11 PV-11 PV-11 PV-11 Cycle Cycle Cycle Cycle Cycle Cycle Cycle Cycle Cycle Cycle Cycle Cycle Cycle Cycle Cycle Cycle Cycle, Cycle Cycle Cycle Cycle Cycle Cycle Full Cycle Internal Inspection, PV-9
.~GAL RHR (Relief Valves)74-.71 74-72 74-73 74 74 74-75 74-77 74-78 74-96 74-97 74-100 74-101 74-98 74-99 74-686 74-509A 74-509B 74-509C 74-509D 74-587A 74-587B 74-659 (U-28 3)(U-18 2)A A B A A A A B B B B B B TEST ZBKKFJLX Q Q Q Q Q Cold Shutdown Cold Shutdown Q Q Q Q Q Q 60 Months 60 Months 60 Months 60 Months 60 Months 60 Months 60 Months 60 Months Full Cycle Full Cycle Full Cycle Full Cycle Full Cycle Full Cycle Full Cycle Full Cycle Full Cycle Full Cycle Full Cycle Full Cycle Full Cycle Meets IWV-3510 Meets IWV-3510 Meets IWV-3510 Meets IWV-3510 Meets IWV-3510 Meets IWV-3510 Meets IWV-3510 Meets IWV-3510 RHR (Check Valves)Core Spray 74-559A 74-559B 74-559C 74-559D 74-661 74-662 74-560A 74-5608 74<<560C 74-560D 74-792 74-804 74-802 74-803 75-2 75-9 75-11 75-22 75-23 75-25 75-26 75-30 75-37 C C C C AC AC C C C C C C C C B B B B B A AC B B Q Q Q Q Operating Cycle Operating Cycle Q Q Q Q Q Q Q Q Q Q Q Q Q Cold Shutdown Cold Shutdown Q Q Full Cycle Full Cycle Full Cycle.Full Cycle Full Cycle, PV-8 Full Cycle, PV-8 Full Cycle Full Cycle Full Cycle Full Cycle Full Cycle, PV-12 Full Cycle, PV-12 Full Cycle, PV-12 Full Cycle, PV-12 Full Cycle Full Cycle Full Cycle Full Cycle~Full Cycle Full Cycle Full Cycle Full Cycle Full Cycle
)LEAK TEST QKKQQBX GEQXKK Core Spray (Continued) 75-39 B 75-50 B 75-51 B 75-53 A 75-54 AC 75-57 A 75-58 A Q Q Q Cold Shutdown<<Cold Shutdown Q Q Full Cycle Full Cycle Full Cycle Full Cycle Full Cycle Full Cycle Full Cycle Core Spray (Check Valve)Core Spray (Relief Valves)Floor and Equipment Drains 75-537A 75-537B 75-537C 75-537D 75-570A 75-570B 75-570C 75-570D 75-606 75-607 75-609 75-610 75-507A 75-507B 75-507C 75-507D 75-543A 75-543B 77-2A 77-2B 77-15A 77-15B C C C C C C C C C C C C C C C C C C A A A A Q Q Q Q Q Q.Q Q Q Q 60 Months 60 Mont;hs 60 Mont;hs 60 Mont;hs 60 Months 60 Months Q Q Q Q Full Cycle Full Cycle Full Cycle Full Cycle Full Cycle Full Cycle Full Cycle Full Cycle Full Cycle, PV-12 Full Cycle, PV-12 Full Cycle, PV-12 Full Cycle, PV-12 Meets IWV-3510 Meets IWV-3510 Meets IWV-3510 Meets IWV-3510 Meets IWV-3510 Meets IWV-3510 Full Cycle Full Cycle, Full Cycle Full Cycle CRD Hydraulic 85-39A-(1-185)
B B 85-39B-(1-185)B B 1 10$of valves every 16 weeks, valves also cycle during any unit scram, all valves also tested each refueling outage Full Cycle Full Cycle Notes: 1.Valve position indication checks are performed per the code, 2.This program is in accordance with Subsection IWV of the 1980 edition through Winter 1980 Addenda of Section XI and is applicable through August 31, 1992.'


This table identifies the Category A valves, and the testing criteria ,'Appendix J, Section XI, or both)to be satisfied at each refueling outage.Testing criteria is based on Items 2, 3, and 4 of t'n'nts , attached to NRC Hughes)of August 8, 1978.(T.A.Ippolito)letter to TVA (N.B.1-14 1-15 1-26 1-27 1-37 1-38 1-51 1-52 1-55 1-56 3-554 3-558 3-568 3-572 43-13 43-14'3-28A 43-28B 43-29A 43-29B 63-525 63-526 68-5o8 68-523 68-55O 68-555 69-1 69-2 69-579 69-624 (Unit 3)71-2 71-3 X X X X X X X X X X X X X X X X X X X X X X X X X X X X X X X X ed' 71-39 71-40 71-14 71-32 71-580 71-592 0 n C X X X X X X M c'n I Yale.~~73-2 73-3 73-81 73-44 73-45 73-23 73-24 73-603 73-609 74 47 74-48 74-53 74-54 74-57 74-58 74-60.74-61 74-67 74-68 74-71 74-72 74 74'74-75'4-77 74-78 74-661'74-662 75-25 75-26 75-53 75-54 75-57 75<<58 77-2A 77-2B 77-15A 77-15B X X X X X X X X X X X X X X X X X X X X X X X X X X'X X X X X X X X X X ASM c X X X X X X.X X X X, X X X X
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C M REQUEST FOR RELIEF LI P~CM Qg~S~CA~)QUQCCggg-RHR Pumps A, B, C, D;HPCI Pump;RCIC Pump;Core Spray, Pumps A, B, C, D;SLC Pumps A, B;RHRSM Pumps A1, A2, A3).B1~B2~B3~C1~C2~C3~D1~D2~D3-Class 2, except RHRSW Pumps which are Class 3.-ECCS and Core Heat Removal (RHRSM Pumps).-Monitoring bearing temperatures during quarterly inservice testing.Bh@MRE LLZKBHKK-All of these pumps, except HPCI and RCIC, have water lubricated pump bearings.The RHR, Core Spray, SLC, and RHRSW pump bearings are lubricated by water supplied by the pump itself.Satisfactory pump operation is indicative of sufficient bearing lubrication.
Mr. Harold R. Denton                                  October 1, 1984 cc (Enclosures):
HPCI and RCIC have oil cooled bearings, but these pumps cannot be operated long enough to reach stable bearing temperatures without overheating the torus and causing plant shutdown.The HPCI bearings, which are instrumented, are monitored during testing.RCIC bearings do not have temperature instrumentation.
U.S. Nuclear Regulatory Commission Region  II ATTN:  James P. O'Reilly, Regional Administrator 101  Marietta Street, Suite 2900 Atlanta, Georgia 30323 Mr. R. J. Clark Browns  Ferry Project Manager U.S. Nuclear Regulatory Commission 7920  Norfolk Avenue Bethesda, Maryland  20814 Mr. E. H. Girard U.S. Nuclear Regulatory Commission Region  II 101  Marietta Street, Suite 2900 Atlanta, Georgia 30323
4 Vibration measurements are taken on all of the Section XI pumps to ensure detection and correction of changes in bearing performance while the pumps are still capable of.satisfactory operation.  


-Standby Liquid Control Pumps-Class 2-ECCS and alternate reactor shutdown capability'.
1 ENCLOSURE  1 ASME SECTION XI INSERVICE PUMP AND VALVE TESTING PROGRAM BROMNS FERRY NUCLEAR PLANT UNITS 1, 2, AND 3 (DOCKET NOS. 50-259, -260, -296) : Inservice Testing Program for    ASME Code  Classes 1, 2, and 3 Pumps : Valves to be Cycled    for ASME  Section XI (IWV-3410, 3510, 3520, and 3610) : Category  A Valves and Testing  Criteria  (Appendix J, Secti'on XI, or both) : Requests  for Relief
-Quarterly measurement of inlet pressure and differential pressure.-During testing these pumps take suction from a test tank that has a relatively small range of level variation during pump operation.
In addition, these are positive displacement pumps whose inlet pressure does not affect pump operating characteristics.
Therefore, differential pressure measurement is not important.
-, Pump discharge pressure will be measured during quarterly testing.A caution note has been placed in the instruction that governs this test so that a minimum level is maintained in the test tank.This ensures discharge pressure is an adequate indication of pump performance.


~C~P~NT-Standby Liquid Control Pumps~CPS.-Class 2 f~CJQg-ECCS.and alternate reactor shutdown capability.
AXiKP29K 1 1 ~
L~3~/XK42Z-Running pumps for five'minutes before measuring parameters.
ItJSERVICE    leSTIN'i  PKCP~uk FOR AS c.
-These pumps are tested by circulating liquid to a test tank for.2 minutes and measuring the volume change in the tank.Running for 5 minutes before measuring parameters is not compatible with the system design.However, a 15-minute functional test which involves recirculating water back to the test tank is run before the system is lined up for the Section XI test require-ment.This 15-minute test is of sufficient length for all parameters to stabilize and the 2-minute test is run immediately afterward.
CODE CLASSES      1, 2,    AtJD 3 PU."'PS The  following table provide" a tabulation of pmps that are subjec'c t'.e testing requirements of Sub"ecticn IMP of Section XI of the I~YZ J.'w ler and Pressur": Vessel Code, 1980 Edi'icn, and Add nda thrcugh Hinter 19tC. Thi s
ZRXXK Measure parameters during 2-minute test.
: p. ograrn will be applicable until August 31, 1992.
C 4 IJ L-All systems-Analysis of test data within 96-hours per 1WP 3220.B~~S.I~LI'F-Due to the time involved in processing surveillance instructions to the reviewer and the possibility of weekends and/or holidays falling between running tests and completely reviewing the results, 96-hours is impractical.
This tabulation identifies the pcnps to be tes'ed, pup code classes, pararne'ers to be rneasur ed, and test irtervals.
Pump parameters of flow rate and differential pressure will be reviewed imnediately after the test by the individual performing the test to verify that they do not fall within the"Required Action Range>>of Table IWP-3100-2.
H~        Ma~         3      Zi        Z                            J ~n 2      NR      Q        0  Q          tJA      0      NR HPCI.                               2      Q      Q        Q  0          tJA  ~   0    0 RCIC                                2      Q      0        Q  0          tJA      0    0<
Complete analysis of test data will be performed within 4 working days of the tests.Xf the pump parameters fall within the"Required Action Range," the individual performing the test will notify the cognizant reviewer and carry out the necessary action required.by the code.  
Core Spray                                  JJR    Q        Q  Q          tJA      Q      JJR Standby Liquid Control              '2            2      lJR      JR      Q  Q          'JA      Q RFIRS''( 1 )                        3      tJR    Q        Q  Q          tJA'          !JR Rotative                                Lor              Lubricant Level or Pressur" P'ifferential H
Pi Speed Inlet Pres ure Pressr:r e            tJR tJA P
tarot tJo Required Avail able Qi            Flow Rate                              H                Mcntrg y Tb            Bearir:g Temperature                    Q                Quarterly V            Vibraticrr Anrpl i tude                A                Annually (1)    These punps are ir a systerr ccexnon to units 1, 2, and 3. Ability to start the pumps will be derncnstrated frcrn each control roan, but canparison to baseline parameters of vibraticn, flew rate, and differential pressure will be perfcrrned for instrumentation in unit 3 only, for ccnsistency of d'ata.


~C pgg5XQ-Installed plant instrumentation and portable instruments used to measure pump parameters.
4 ~
Q~>S QJ~CI~O-1,2,and3-Measurement of pump parameters.
The  following table provides  a  listing of systems, valve numbers, types, categories, test frequencies,   and type of tests for those valves to be I
-Instrunent accuracy shall be within the limits of'Table IMP-4100-1.
cycled in accordance with  ASME  Section XI, IHV-3410, 3510, 3520, and 3610.
-The accuracy of installed plant indicators is~2'5 of full scale.However, the accuracy of installed transmitters and square-rooters is 0.5$and when these are taken into account the instrument loop accuracies are 2.5$and 3.0$for pressure loops and flow loops, respectively.
4
The plant installed instr+vents will continue to be used since any alternate method such as connecting test instrunents into the system or*.replacing plant instrumentation, will not provide sufficient benefit to outweigh the added'cost and manpower of the alternate methods.The portable instrument used to measure vibration amplitude has an accuracy of 11%of full scale.The instrunent has been used from the beginning of the program to collect the vibration data and develop all the vibration baselines that are used in the pump program.Since all other requirements for measuring amplitude (XWP-4520) have been met and since the instrunent used is an accepted standard method for industrial, vibration and measurements, the instrunent will continue to be used.XFAGHG An equipment diagnostic program using much more sophisticated instrunents and methods monitors rotating equipment at the plant and provides much better vibration data on the pumps than the one required data point of the pump program.This program is done in addition to the test requirement.  


S LI F-All valves-A, B, and C-, Various functions-Corrective action on an inoperable valve required before startup per Mf-3417 and IWV-3523.-Limiting conditions for startup have been analyzed in Browns Ferry Technical Specifications, Technical Bases 3.4.B, 4.4, 3 O'As 3'5't 3 O'Ct 3'O'Es 3'5 F Valve'inoperability will preclude unit startup only if the.valve places the system itself in a position of preventing startup per present technical specifications.
TEST XLQD'.              HKQXH<Y Main Steam      1-14            A      Q              Full Cycle 1-15            A      Q              Full Cycle 1-26            A      Q              Full Cycle 1-27            A       Q              Full  Cycle 1-37            A      Q              Full  Cycle 1-38            A      Q              Full  Cycle 1-51            A      Q              Full  Cycle 1-52            A        Q              Full  Cycle Main Steam        1-4             C  60  months        Meets IWV-3510 (Rel'ief Valves)  1-5             C  60  months        Meets IWV-3510 1-18            C  60  months        Meets'IWV-3510 1-19            C    60  months        Meets IWV-3510 1-22            C    60  months        Meets IWV-3510 1-23            C    60  months        Meets IWV-3510 1-30            C    60  months        Meets IWV-3510 1-31            C    60  months        Meets IWV-3510 1-34            C    60  months        Meets IWV-3510 1-41            C    60  months        Meets IWV-3510 1-42            C    60  months        Meets IWV-3510 1-179            C    60  months         Meets Mf-3510 1-180          C    60  months         Meets IWV-3510 Feedwater (Check Valves)   3-554           AC Operating  Cycle    Full  Cycle, PV-8 3-558           AC Operating  Cycle    Full  Cycle, PV-8 3-568           AC Operating  Cycle    Full  Cycle, PV-8 3-572           AC Operating  Cycle    Full  Cycle, PV-8 23-34                                    Full  Cycle 23-40                                  -
fl L P-CRD (Scram Function)-85-39A-(1-185)85-39B-.(1-185)-Provide flow path for water for control rod scrams.-Exercised once every 3 months.-Cycling these valves requires scramming a control rod.There are 185 control rods in the reactor.Scramming every rod once every three months is not practical for the following reasons.a.A power reduction is required to test the scram function.Reducing power for the length of time required to scram 185 rods places an unfair burden on the licensee.b.'uel preconditioning must follow this power reduction to avoid possible fuel damage.The longer the reduction in power, the longer the pr'econditioning.
Full  Cycle 23-46                                    Full  Cycle 23-52                                    Full  Cycle 23-57 ( U-142)                          Full  Cycle RHRSW
10$of the rods will be scram testd every sixteen weeks, and all rods will be scram tested during refueling, per present Technical Specifications.
,(Check Valves)   23-502          C      Q              Full Cycle 23-506          C      Q              Full, Cycle 23-522          C      Q              Full Cycle 23-526          C      Q              Full Cycle 23-542          C      Q              Full Cycle 23-546          C      Q              Full Cycle 23-561          C      Q              Full Cycle 23-565          C      Q              Full Cycle 23-579  (510 U1) C      Q              Full Cycle 23-580  (530 U1) C      Q              Full Cycle 23-581  (550 U1) C      Q              Full Cycle 23-582  (569 U1) C      Q              Full Cycle 23-591          C      Q              Full Cycle 23-594          C      Q          -   Full Cycle 23-597          C      Q              Full Cycle 23-588          C      Q              Full Cycle
Xn addition, all rods are provided with the same test during normal operation when the unit scrams.
lt LlE&5XF85L MCHRQHlBG5 (VALVES)-Feedwater-3-554, 3-558, 3-568, 3 572 Standby Liquid Control-63-525, 63-526 Reactor Recircultion System-68-508, 68-523, 68-550, 68-555 Reactor Water Cleanup-69-579, 69-624 (Unit 3 only)Residual Heat Removal-74-661, 74-662-AC ZEKTXQH-All are containment isolation, plus;prevents backflow in feedwater lines (System 3), prevents backflow in RWCU System (System 69), and thermal expansion relief (System 74).~ASS QQ jgL:gF-Exercise valves for operability quarterly.
-All of these valves are check valves whose operation cannot be verified during plant operation.
Testing requires entry into primary containment, stopping RWCU system operation (System 69)or inter rupting seal water to the recirculation pumps (System 68)which is very likely to cause seal damage.-Valves 74-661, 662 are not required to change position and hence, are not required to be tested for operability.
~BHbXI'.-Valves will be tested in accordance with 10 CFR 50, Appendix J, at each refueling outage.
L~XIZQL QZEQHKHX5 (VALVES)-Reactor Core Isolation Cooling-71-508 High Pressure Coolant Injection-73-517 ZUK<UQH-Valves present backflow to the torus from the RCIC and HPCI, respectively.
-Valves cannot be cycled without introducing torus water into the vessel.This water is of such quality that it should not be introduced into the vessel unless an accident has occurred.XLZ2583X-Valve internals will be visually and manually checked each refueling outage by removal of valve access plates.Testing check valves each refueling outage is in line with the'RC's latest philosophy on testing check valves.


~Y~M MCKQKHXQ (VALVES)-67-502, 582, 622, 619 67-648, 649, 541, 542, 558, 559, 638, 639, 659, 657 656, 584, 585, 556, 598, 600, 601, 660, 659, 838, 839, 843, 844 1-67-634, 635, 528, 529, 521, 522, 630, 631, 624, 625, 514, 515, 627, 628, 507, 508 3-67-723, 724, 725, 726, 713, 714, 715, 716, 703, 704, 705, 706, 695, 696, 693, 694 3-67-735, 736, 737, 738 j~UC'Igg-All required to pass rated flow to emergency coolers, plus backseat upon loss of one of the two EEL headers (except 3-67-735, 736, 737,'738 and 67-838, 839, 843, 844)-Operability test quarterly WXQEKTK 3XGX3&#xb9;-Backflow testing these valves individually cannot be performed due to lack of test connections between valves.-These valves will be part stroke-tested quarterly (except 3-67-735, 736, 737, 738)and an internal inspection done each.refueling outage.  
TEST
-High Pressure Coolant Injection-73-633, 634, 635, 636 Reactor Core Isolation Cooling-71-597, 598, 599)600-HPCI/RCIC Turbine Exhaust Vacuum Relief-Exercise each valve for operability quarterly-Each valve cannot be checked individually due to lack of isolation valves.The four valves are in a"one-out-of-two-taken twice" arrangement, so there is redundancy in case a valve fails to open.-Test each arrangement of valves quarterly.
~Y~gM                        MCXKQBX  GKQUKKX              P  OF SLC            63-514        C          Q          Full  Cycle (Check Valves) 63-516        C          Q          Full  Cycle 63-525        AC    Operating Cycle Full  Cycle, PV-8 63-526        AC    Operating Cycle Full  Cycle, PV-8 SLC            63-512              Operating Cycle Tech Spec 4.4.A.2 (Relief Valves) 63-513              Operating Cycle Tech Spec 4.4.A.2 SLC  (Explosive 63-SA                2-year Cycle    IWV-3610 Valves)      63-SB                2-year Cycle    1WV-3610 EE%            67-13                                Full Cycle 67-14                                Full. Cycle 67-17                                Full Cycle 67-18                                Full  Cycle 67-21                                Full  Cycle 67-22                                Full  Cycle 67-25                                Full  Cycle 67-26                                Full  Cycle 67-48                                Full  Cycle 67-49                                Full  Cycle EEL            67-502        C          Q          Part  Cycle, PV-,10 (Check Valves)  67-582        C          Q          Part  Cycle, PV-10 67-622        C          Q          Part  Cycle, PV-10 67-619        C          Q          Part  Cycle, PV-10 67-541        C          Q          Part  Cycle, PV-10 67-542        C          Q          Part  Cycle, PV-.10 67-584        C          Q          Part  Cycle, PV-10 67-585        C          Q          Part  Cycle, PV-10 67-648        C          Q          Part  Cycle, PV-10 67-649        C          Q          Part  Cycle, PV-10 67-656        C          Q          Part  Cycle, PV-10 67-657                    Q          Part  Cycle, PV-10 67-559                    Q          Part  Cycle, PV-10 67>>558                    Q          Part  Cycle, PV-10 67-638                    Q          Part  Cycle, PV-10 67<39                    Q          Part  Cycle, PV-10 67-600                    Q          Part  Cycle, PV-10 67-601                    Q          Part  Cycle, PV-10 67-659                    Q          Part  Cycle, PV-10 67-660                    Q          Part  Cycle, PV-10 67-556                    Q          Part  Cycle, PV-10 67-598                    Q          Part  Cycle, PV-10 67693 (U-3)              Q          Part  Cycle, PV-10 67-694 (U-3)              Q          Part  Cycle, PV-10 67%95 (U-3)              Q          Part  Cycle, PV-10 67-696 (U-3)              Q          Part  Cycle, PV-10 67-705 (U-3)              Q          Part  Cycle, PV-10 67-706 (U-3)              Q          Part  Cycle, PV-10 67-703 (U-3)              Q          Part  Cycle, PV-10 67-704 (U-3)              Q          Part  Cycle, PV-10
It'I REQUEST FOR RELIEF-PV-12 MCHKHKHXQ-Core Spray-75-609, 610 75-606, 607-74-792, 804 74-802, 803 XIX,-Prevents backflow into the keep fill system (PSC Head Tank)-Exercise each valve for operability quarterly ZKU~IE L4TQ5hXK 3XSLQKi-Each individual valve cannot be tested due to lack of test connections.
 
-Quarterly testing of pairs of valves together plus an internal inspection each refueling outage.  
TEST KQBX ZEK8LKKX EECM          67-528  (U-1) C        Q      Part Cycle,  PV-10 (Check Valves 67-529  (U-1) C        Q      Part Cycle,  PV-10
'(dl ENCLOSURE 2 RESPONSE TO NRC REQUEST FOR ADDITIONAL INFORMATION REGARDING INSERVICE PUMP AND VALVE TESTING PROGRAM BROWNS FERRY NUCLEAR PLANT UNITS 1, 2, AND 3 (
-
Continued) 67%34  (U-1) C        Q      Part Cycle,  PV-10 67%35  (U-1) C        Q      Part Cycle,  PV-10 67-521  (U-1) C        Q      Part Cycle,. PV-10 67-522  (U-1) C        Q      Part Cycle,  PV-10 67-630  (U-1) C        Q      Part Cycle,  PV-10 67-631 (U-1)  C        Q      Part Cycle,  PV-10 67-624 (U>>1)  C        Q      Part Cycle,  PV-10 67-625 (U-1)  C        Q      Part Cycle,  PV-10 67-514 (U-1)  C        Q      Part Cycle,  PV-10 67-515 (U-1)  C        Q      Part Cycle,  PV-10 67-627 (U-1)  C        Q      Part Cycle,  PV-10 67-628 (U-1)  C        Q      Part Cycle,  PV-10 67-507 (U-1)  C        Q      Part Cycle,  PV-10 67-508 (U-1)  C        Q      Part Cycle,  PV-10 67-838        C        Q    ,Part Cycle,  PV-10 67-839        C        Q      Part Cycle,  PV-10 67-843        C        Q      Part Cycle,  PV-10 67-844        C        Q      Part Cycle,  PV-10 67-715 (U-3)          Q      Part Cycle,  PV-10 67-716 (U-3)          Q      Part Cycle,  PV-10 67-713 (U-3)          Q      Part Cycle,  PV-10 67-714 (U-3)          Q      Part Cycle,  PV-10 67-723 (U-3)          Q    Part  Cycle,  PV-10 67-724 (U-3)          Q      Part Cycle,  PV-10 67-725 (U-3)          Q      Part Cycle,  PV-10 67-726 (U-3)          Q    Part  Cycle,  PV-10 67-737 (U-,3)          Q    Part  Cycle,  PV-10 67-738 (U-3)          Q    Part  Cycle,  PV-10 67-735 (U-3)          Q      Part  Cycle,  PV-10 67-736 (U-3)          Q      Part  Cycle,  PV-10
 
TEST
                              ~CKBX      HMlKhLCX Recirculation    68-3                  Cold Shutdown      Full Cycle Loops            68-79                  Cold Shutdown      Full Cycle Recirculation    68-508          AC    Operating  Cycle  Full Cycle,  PV-8 Loops            68-523          AC    Operating  Cycle  Full Cycle,  PV-8 (Check Valves)  68-550          AC    Operating  Cycle  Full Cycle,  PV-8 68-555          AC    Operating  Cycle  Full Cycle,  PV-8 RWCU            69-1                                      Full Cycle 69-2                                      Full Cycle RWCU            69-579        -AC    Operating Cycle    Full Cycle,  PV-8 (Check Valves)  69-624 (U-3)    AC    Operating Cycle    Full Cycle,  PV-8 RCIC            71-2            A      Cold Shutdown      Full Cycle 71-3            A      Cold Shutdown      Full Cycle 71-5            B          Q            Full Cycle 71-6A          B          Q            Full Cycle
                ,71-6B          B          Q            Full Cycle 71-34          B          Q            Full Cycle 71-8            B          Q            Full Cycle 71-9            B          Q            Full Cycle 71-10          B          Q            Full Cycle 71-17          B          Q            Full Cycle 71-18          B          Q            Full Cycle 71-25          B          Q            Full Cycle 71-37          B      Cold Shutdown      Full Cycle 71-39          A      Cold Shutdown      Full Cycle 71-40          AC    Cold Shutdown      Full Cycle 71-22          B          Q            Full Cycle RCIC            71-580          AC          Q            Full Cycle (Check Valves)  71-597          C          Q            Full Cycle,  PV-11 71-598          C          Q            Full Cycle,  PV-11 71-599          C          Q            Full Cycle,  PV-11 71-600          C          Q            Full Cycle,  PV-11 71-508          C  Operating Cycle    Internal Inspection, PV-9 71-592          AC          Q            Full Cycle, PV-11 RCIC            71-543                60 Months          Meets IWV-3510 (Relief Valves)  71-503                60 months          Meets IWV-3510 HPCI            73-81                  Cold Shutdown      Full Cycle 73-2                  Cold Shutdown      Full Cycle 73-3                  Cold Shutdown      Full Cycle 73-5                        Q            Full Cycle
 
TEST MCZKEK    ZlKQL~~Y HPCI ~
73-6A    B          Q            Full Cycle (Continued)      73-6B    B          Q            Full  Cycle 73-16    B          Q            Full Cycle 73-18  B          Q            Full Cycle 73-19  B          Q            Full Cycle 73-26    B          Q          Full  Cycle 73-27    B          Q          Full  Cycle 73-34    B    Cold Shutdown    Full  Cycle 73-43    B          Q          Full  Cycle 73 44    A    Cold Shutdown    Full  Cycle
                '73-45    AC    Cold Shutdown    Full  Cycle 73-30    B          Q          Full  Cycle HPCI            73-574        60 Months        Meets IHV-3510 (Relief Valves)  73-506        60 Months        Meets IHV-3510 73-559  C          Q          Full  Cycle HPCI            73-517  C  Operating Cycle  Internal  Inspection, PV-9 (Check Valves)  73-603  AC          Q          Full  Cycle 73-609  AC          Q          Full  Cycle 73-633  C          Q          Full  Cycle,  PV-11 73-634  C          Q          Full  Cycle,  PV-11 73-635  C          Q          Full  Cycle,  PV-11 73-636  C          Q          Full  Cycle, PV-11 RHR              74-1    B          Q          Full  Cycle 74-2    B          Q          Full  Cycle 74-7    B          Q          Full  Cycle 74-12    B          Q          Full  Cycle 74-13    B          Q          Full  Cycle 74-24    B          Q          Full  Cycle 74-25    B          Q          Full  Cycle 74-30    B          Q          Full  Cycle 74-35    B          Q          Full  Cycle 74-36    B          Q          Full  Cycle 74 47    A    Cold Shutdown      Full  Cycle 74-48    A    Cold Shutdown      Full  Cycle 74-52    B          Q            Full  Cycle 74-53    A    Cold Shutdown      Full  Cycle 74 54    AC  Cold Shutdown      Full  Cycle 74-57    A          Q            Full  Cycle 74-58    A          Q            Full  Cycle, 74-59    B          Q            Full  Cycle 74-60    A          Q            Full  Cycle 74-61    A          Q.          Full  Cycle 74-66    B        'Q            Full  Cycle 74-67  A    Cold Shutdown      Full  Cycle 74-68  AC    Cold Shutdown      Full  Cycle
 
TEST
. ~GAL                                  ZBKKFJLX 74-.71          A        Q          Full  Cycle 74-72          A        Q          Full  Cycle 74-73          B        Q          Full  Cycle 74 74          A        Q          Full  Cycle 74-75          A        Q          Full  Cycle 74-77          A  Cold Shutdown    Full  Cycle 74-78          A  Cold Shutdown    Full  Cycle 74-96          B        Q          Full  Cycle 74-97          B        Q          Full  Cycle 74-100 (U-28 3) B        Q          Full  Cycle 74-101 (U-18 2) B        Q          Full  Cycle 74-98          B        Q          Full  Cycle 74-99          B        Q          Full  Cycle RHR            74-686            60  Months        Meets  IWV-3510 (Relief Valves) 74-509A            60  Months        Meets  IWV-3510 74-509B            60  Months        Meets  IWV-3510 74-509C            60  Months        Meets  IWV-3510 74-509D            60  Months        Meets  IWV-3510 74-587A            60  Months        Meets  IWV-3510 74-587B            60  Months        Meets  IWV-3510 74-659            60  Months        Meets  IWV-3510 RHR            74-559A        C        Q          Full  Cycle (Check Valves)  74-559B        C        Q          Full  Cycle 74-559C        C        Q          Full  Cycle.
74-559D        C        Q          Full  Cycle 74-661          AC Operating Cycle  Full  Cycle,  PV-8 74-662          AC Operating Cycle  Full  Cycle,  PV-8 74-560A        C        Q          Full  Cycle 74-5608        C        Q          Full  Cycle 74<<560C        C        Q          Full  Cycle 74-560D        C        Q          Full  Cycle 74-792          C        Q          Full  Cycle,  PV-12 74-804          C        Q          Full  Cycle,  PV-12 74-802          C        Q          Full  Cycle,  PV-12 74-803          C        Q          Full  Cycle,  PV-12 Core Spray      75-2            B        Q          Full  Cycle 75-9            B        Q          Full  Cycle 75-11          B        Q          Full  Cycle 75-22          B        Q          Full  Cycle 75-23          B        Q        ~
Full  Cycle 75-25          A  Cold Shutdown    Full  Cycle 75-26          AC Cold Shutdown    Full  Cycle 75-30          B        Q          Full  Cycle 75-37          B        Q          Full  Cycle
 
TEST
                    )LEAK        QKKQQBX    GEQXKK Core Spray      75-39            B            Q              Full  Cycle (Continued)      75-50            B            Q              Full  Cycle 75-51            B            Q              Full  Cycle 75-53            A      Cold Shutdown    <<
Full  Cycle 75-54            AC    Cold Shutdown        Full  Cycle 75-57            A            Q              Full  Cycle 75-58            A          Q                Full  Cycle Core Spray        75-537A          C          Q              Full  Cycle (Check Valve)      75-537B          C          Q              Full  Cycle 75-537C          C          Q              Full  Cycle 75-537D          C          Q              Full  Cycle 75-570A          C          Q              Full  Cycle 75-570B          C          Q              Full  Cycle 75-570C          C          .Q              Full  Cycle 75-570D          C          Q              Full  Cycle 75-606            C                          Full  Cycle,  PV-12 75-607            C                          Full  Cycle,  PV-12 75-609            C          Q              Full  Cycle,  PV-12 75-610            C          Q              Full  Cycle,  PV-12 Core Spray        75-507A            C  60  Months            Meets  IWV-3510 (Relief Valves)    75-507B            C  60  Mont;hs          Meets  IWV-3510 75-507C            C    60  Mont;hs          Meets  IWV-3510 75-507D            C    60  Mont;hs          Meets  IWV-3510 75-543A            C  60  Months            Meets  IWV-3510 75-543B            C    60  Months          Meets    IWV-3510 Floor  and        77-2A              A          Q              Full  Cycle Equipment          77-2B              A          Q              Full  Cycle, Drains            77-15A            A          Q              Full  Cycle 77-15B            A          Q              Full  Cycle CRD  Hydraulic    85-39A-(1-185) B  B    10$ of valves        Full Cycle 85-39B-( 1-185) B  B    every 16 weeks,      Full Cycle 1
valves also cycle during any  unit  scram, all  valves also tested each refueling outage Notes:
: 1. Valve position indication checks are performed per the code,
: 2. This program is in accordance with Subsection    IWV  of the  1980  edition through Winter 1980 Addenda of Section XI and    is applicable    through August 31, 1992.
            '
 
This table  identifies the          Category A valves, and the testing  criteria
, 'Appendix J, Section XI, or both) to            be  satisfied at each refueling outage.
Testing  criteria is        based on Items 2, 3, and 4    of  t'n      '
nts
                              ,  attached to  NRC (T.A. Ippolito)  letter to  TVA (N. B.
Hughes)  of August 8, 1978.
ed' 1-14                                  X 1-15                                  X 1-26                                  X 1-27                                  X 1-37                                  X 1-38                                  X 1-51                                  X 1-52                                  X 1-55                                  X 1-56                                  X 3-554                                  X 3-558                                  X 3-568                                  X 3-572                                  X 43-13                                  X 43-14                                  X
                '3-28A X
43-28B                                X 43-29A                                X 43-29B                                X 63-525                                X 63-526                                X 68-5o8                                X 68-523                                X 68-55O                                X 68-555                                X 69-1                                  X 69-2                                  X 69-579                                X 69-624        (Unit 3)                X 71-2                                  X 71-3                                  X
 
0 n C M c'n I 71-39    X 71-40    X 71-14    X 71-32    X 71-580  X 71-592  X
 
Yale.~~    ASM c 73-2  X 73-3  X 73-81  X 73-44  X 73-45  X 73-23  X 73-24  X 73-603 X 73-609 X 74 47  X        X 74-48  X        X 74-53  X        X 74-54  X        X 74-57  X 74-58  X 74-60. X 74-61  X 74-67  X        X 74-68  X        X.
74-71  X 74-72  X 74 74  X
'74-75  X
'4-77    X        X 74-78  X        X 74-661 X'      X
'74-662          X, 75-25  X        X 75-26  X        X 75-53  X        X 75-54  X        X 75-57  X 75<<58  X 77-2A  X 77-2B  X 77-15A X 77-15B X
 
C M REQUEST FOR RELIEF
 
LI  P
~CM Qg~S - RHR Pumps A, B, C, D; HPCI Pump; RCIC Pump; Core Spray, Pumps A, B, C, D; SLC Pumps A, B; RHRSM Pumps A1, A2, A3). B1 ~ B2~ B3~ C1 ~ C2~ C3~ D1 ~ D2~ D3
~CA~)    - Class 2, except  RHRSW Pumps  which are Class 3.
QUQCCggg - ECCS  and Core Heat Removal (RHRSM Pumps).
        - Monitoring bearing temperatures during quarterly inservice testing.
Bh@MRE
        - All of  these pumps, except HPCI and RCIC, have water lubricated pump  bearings. The RHR, Core Spray, SLC, and RHRSW pump bearings are lubricated by water supplied by the pump itself.
Satisfactory pump operation is indicative of sufficient bearing lubrication. HPCI and RCIC have oil cooled bearings, but these pumps cannot be operated long enough to reach stable bearing temperatures without overheating the torus and causing plant shutdown. The HPCI bearings, which are instrumented, are monitored during testing. RCIC bearings do not have temperature instrumentation.
4 LLZKBHKK Vibration measurements are taken on all of the Section XI pumps to ensure detection and correction of changes in bearing performance while the pumps are still capable of .satisfactory operation.
 
Standby    Liquid Control  Pumps
-  Class 2 ECCS and    alternate reactor shutdown capability'.
Quarterly measurement    of inlet pressure  and  differential pressure.
- During  testing these  pumps  take suction from  a test tank that has a  relatively small  range  of level variation during pump operation. In addition, these are positive displacement pumps whose inlet pressure does not affect pump operating characteristics. Therefore, differential pressure measurement is not important.
Pump
  ,      discharge pressure will be measured during quarterly testing. A caution note has been placed in the instruction that governs this test so that a minimum level is maintained in the test tank. This ensures discharge pressure is an adequate indication of pump performance.
 
~C~P~NT  Standby  Liquid Control  Pumps
~CPS  . - Class 2 f~CJQg  - ECCS.and  alternate reactor shutdown capability.
L Running pumps  for five'minutes before measuring parameters.
~3~/
XK42Z    - These pumps are tested by circulating liquid    to a test tank for.
2 minutes and measuring the volume change in    the tank. Running for 5 minutes before measuring parameters is    not compatible with the system design. However, a 15-minute functional test which involves recirculating water back to the test tank is run before the system is lined up for the Section XI test require-ment. This 15-minute test is of sufficient length for all parameters to stabilize and the 2-minute test is run immediately afterward.
ZRXXK      Measure parameters  during 2-minute test.
 
C 4
IJ
 
L
          - All systems
          - Analysis of test data within 96-hours per  1WP  3220.
B~~S
. I~LI 'F - Due  to the time involved in processing surveillance instructions to the reviewer and the possibility of weekends and/or holidays falling between running tests and completely reviewing the results, 96-hours is impractical.
Pump parameters of flow rate and differential pressure will be reviewed imnediately after the test by the individual performing the test to verify that they do not fall within the "Required Action Range>> of Table IWP-3100-2. Complete analysis of test data will be performed within 4 working days of the tests. Xf the pump parameters fall within the "Required Action Range," the individual performing the test will notify the cognizant reviewer and carry out the necessary action required .
by the code.
 
~C  pgg5XQ  Installed  plant instrumentation    and portable instruments used to measure pump parameters.
Q~>S    -1,2,and3 QJ~CI~O  Measurement  of  pump parameters.
Instrunent accuracy    shall  be within the limits of'Table IMP-4100-1.
            -  The accuracy  of installed plant indicators is    ~2'5 of full scale. However, the accuracy of installed transmitters and square-rooters is 0.5$ and when these are taken into account the instrument loop accuracies are 2.5$ and 3.0$ for pressure loops and flow loops, respectively. The plant installed instr+vents will continue to be used since any alternate method such as connecting test instrunents into the system or* .
replacing plant instrumentation, will not provide sufficient benefit to outweigh the added'cost and manpower of the alternate methods.
The portable  instrument used to measure vibration amplitude has an accuracy  of  11% of full scale. The instrunent has been used from the beginning of the program to collect the vibration data and develop all the vibration baselines that are used in the pump program. Since all other requirements for measuring amplitude (XWP-4520) have been met and since the instrunent used is an accepted standard method for industrial, vibration and measurements, the instrunent will continue to be used.
XFAGHG        An equipment  diagnostic program using much more sophisticated instrunents and methods monitors rotating equipment at the plant and provides much better vibration data on the pumps than the one required data point of the pump program. This program is done in addition to the test requirement.
 
S        LI F
- All valves
- A, B, and C
-, Various functions Corrective    action on an inoperable valve required before startup per Mf-3417    and IWV-3523.
-  Limiting conditions for startup have been analyzed in Browns Ferry Technical Specifications, Technical Bases 3.4.B, 4.4, 3 O'As  3'5 't  3 O'Ct 3'O'Es 3'5 F
.
Valve 'inoperability will preclude unit startup only  if the valve places the system itself in a position of preventing startup per present technical specifications.
 
fl L    P CRD (Scram    Function) 39A  (1-185) 85-39B -. (1-185)
- Provide flow path for water      for control rod scrams.
Exercised once    every 3 months.
Cycling  these valves requires scramming a control rod. There are 185  control rods in the reactor. Scramming every rod once every  three  months is not practical for the following reasons.
: a. A power    reduction  is required to test the scram function.
Reducing power    for the length of time required to scram 185 rods places an    unfair burden on the licensee.
b.'uel preconditioning must follow this power reduction to avoid possible fuel damage. The longer the reduction in power, the longer the pr'econditioning.
10$  of the rods will be    scram testd every sixteen weeks, and all  rods  will be  scram  tested during refueling, per present Technical Specifications. Xn addition, all rods are provided with the same test during normal operation when the unit scrams.
 
lt LlE
&5XF85L MCHRQHlBG5  Feedwater    3-554,  3-558, 3-568, 3 572 (VALVES)  Standby Liquid Control 525, 63-526 Reactor Recircultion System  68-508, 68-523, 68-550, 68-555 Reactor Water Cleanup 579, 69-624 (Unit 3 only)
Residual Heat Removal 661, 74-662
            - AC ZEKTXQH    - All are  containment isolation, plus; prevents backflow in feedwater lines (System 3), prevents backflow in RWCU System (System 69), and thermal expansion relief (System 74).
            - Exercise valves  for operability quarterly.
~ASS QQ jgL:gF      All  of these valves are check valves  whose operation cannot be verified during plant operation. Testing requires entry into primary containment, stopping RWCU system operation (System 69) or inter rupting seal water to the recirculation pumps (System 68) which is very likely to cause seal damage.
Valves 74-661, 662 are not required to change position and hence, are not required to be tested for operability.
~BHbXI'.
Valves  will be  tested in accordance with  10 CFR 50, Appendix J, at each  refueling outage.
 
L
~XIZQL QZEQHKHX5  Reactor Core  Isolation Cooling 508 (VALVES)   High Pressure  Coolant Injection  73-517 ZUK<UQH    - Valves present backflow to the torus from the RCIC and HPCI, respectively.
          - Valves  cannot be cycled without introducing torus water into the vessel. This water is of such quality that  it  should not be introduced into the vessel unless an accident has occurred.
XLZ2583X Valve  internals will be visually and manually checked each refueling outage by removal of valve access plates. Testing check valves each refueling outage is in line with the'RC's latest philosophy on testing check valves.
 
~Y~M MCKQKHXQ    502, 582, 622, 619 (VALVES)  67-648, 649, 541, 542, 558, 559, 638, 639, 659, 657 656, 584, 585, 556, 598, 600, 601, 660, 659, 838, 839, 843, 844 1-67-634, 635, 528, 529, 521, 522, 630, 631, 624, 625, 514, 515, 627, 628, 507, 508 3-67-723, 724, 725, 726, 713, 714, 715, 716, 703, 704, 705, 706, 695, 696, 693, 694 3-67-735, 736, 737, 738 j~UC 'Igg   - All required   to pass rated flow to emergency coolers, plus backseat upon loss of one of the two EEL headers (except 3-67-735, 736, 737, '738 and 67-838, 839, 843, 844)
Operability   test quarterly
            - Backflow testing these valves individually cannot be performed due to lack of test connections between valves.
WXQEKTK      These valves will be part stroke-tested quarterly (except 3 3XGX3&#xb9;        735, 736, 737, 738) and an   internal inspection done each.
refueling outage.
 
- High Pressure Coolant Injection 73-633, 634, 635, 636 Reactor Core Isolation Cooling 597, 598, 599) 600
- HPCI/RCIC Turbine Exhaust Vacuum   Relief Exercise each valve for operability quarterly
- Each valve cannot be checked individually due to lack of isolation valves. The four valves are in a "one-out-of
  -two-taken twice" arrangement, so there is redundancy in case a valve fails to open.
- Test each arrangement of valves quarterly.
 
It
'I
 
REQUEST FOR RELIEF - PV-12 MCHKHKHXQ - Core Spray   609, 610 75-606, 607 792, 804 74-802, 803 Prevents backflow into the keep   fill system (PSC Head Tank)
: XIX, Exercise each   valve for operability quarterly ZKU~IE   - Each individual valve cannot   be tested due to lack of test connections.
L4TQ5hXK 3XSLQKi    Quarterly   testing of pairs of valves together plus   an internal inspection each refueling outage.
 
  '(
dl
 
ENCLOSURE 2 RESPONSE TO NRC REQUEST FOR ADDITIONAL INFORMATION REGARDING INSERVICE PUMP AND VALVE TESTING PROGRAM BROWNS FERRY NUCLEAR PLANT UNITS 1, 2, AND 3
(


==Reference:==
==Reference:==
NRC    Letter  from D. B. Vassallo to H. G. Parris dated February 10, 1984)
NOTE:    TVA's philosophy    in writing the  pump and valve testing program has been to include those systems    and piping that carry water, steam, or radioactive material. We see no defined regulatory basis for the NRC staff to increase the scope of testing in the inservice pump and valve testing program, as is apparently the intent of questions 1 and 2. We, therefore, plan to respond only to those water, steam, or radioactive waste-containing components in questions land 2, and request that our submittals be reviewed against currently defined regulatory requirements.
: 1.  , NRC REQUEST The pump  portion of the IST program was reviewed to verify that all pumps that are important to safety are included in the program and are subjected to the testing required by the ASME Code. In the staff's judgment there are additional systems wherein the associated pumps should be in the program. These systems are:
Plant Service Water PSC Head  Tank Fuel Oil Transfer Please justify the omission of the pumps      in, these systems or revise the IST program to include them.
TVA RESPONSE Plant Service Water Pumps--The plant service water system performs no safety-related function; hence, its pumps are not considered in the scope of Section XI.
Pressure Suppression Chamber (PSC) Head Tank--The pumps in the Keep Fill system do not perform an active safety function in "keeping the core spray and RHR systems charged.      The head tank water volume maintains these systems charged at the    required  pressure. The head tank pumps maintain the proper ahead tank level with occasional makeup to the head tank.
Fuel Oil Transfer    See note above.
: 2. NRC REQUEST Likewise, in the    staff's  judgement the  following valves should  be  in the IST program:
Combustible Gas Control System valves Primary Containment Atmosphere valves Fuel Oil Transfer System valves Transverse In-Core Probe valves Valves in the portions of the Instrument and Control Air System that perform a function important to safety Valves in ventilating systems that perform a function important to safety Sampl'ing System valves Torus Drain Valves Drywell - Pressure Suppression Chamber (PSC) and      PSC  Reactor Building  vacuum  breakers SRV discharge line vacuum br eakers (Valves 10-506, 507, 519, etc.)
Primary Containment H2 and 02 Analyzer Valves EECM valves for the Unit 1 and 2 Diesel Generator Engine Coolers Diesel Generator Air Start Valves All relief valves important to safety except ADS valves (e.g.,
valves 75-543 A and B)
            . Keep-Fill valves in Core Spray System (e.g., valves 75-609 and -610)
Please provide technical justification for the omission of these valves or revise the IST program to include them.
TVA RESPONSE Combustible Gas Control System Valves--See note above.
I Primary Containment Atmosphere Valves--See note above.
Fuel Oil Transfer System Valves--See note above.
Traversing In-Core Probe Valves A
See note above.
Valves in Instrument and Control      Air System--See note above.
I Valves in Ventilating Systems--See      note above.
Sampling System Valves The sampling system valves (43-13, 14, 28A, 28B, 29A, and 29B), which perform a containment isolation function and are tested, in accordance with the criteria in Appendix J, are identified as Clas's A valves and included in Attachment 3 of the pump and valve program.
0 r
Torus Drain Valves The torus drain valves (75-57, 58) that perform a containment isolation function are included in the program.
Drywell PSC  and PSC-Reactor  Building Vacuum  Breakers--See note above.
SRV  Discharge Line Vacuum Breakers--See    note above.
Primary Containment    H2 and 02  Analyzer Valves--See note above.
EECW  Valves for units    1 and 2 Diesel Generator Engine Coolers--These valves are tested per Section XI requirements but were inadvertently      left out of the program submittal. They are included in the updated program.
Diesel Generator Air Start Valves--See note above.
All Relief    Valves Important to Safety--We have reviewed the various safety systems and have included those      relief valves determined to be needed in our program.
Keep  Fill Valves    in Core Spray and RHR Systems These valves have been included in the progr    am as indicated in the valve listing with the conditions noted  in Request  for Relief PV-12.
: 3. NRC REQUEST You  requested  relief for all pumps from the requirements of paragraph IWP-3220  that all pump test data be analyzed within 96 hours after completion of the test. We agree that a delay of an additional day before pump test data is completely analyzed is not significant if there is no delay in performing preliminary reviews of test data (including vibration levels) immediately after the test, and any pumps whose measured test parameters fall within the Code "Required Action Range" are immediately declared inoperable upon completion of the preliminary reviews. Confirm that this is your intent.
TVA RESPONSE A  preliminary analysis is performed on pump test data (including vibration) immediately after the test. Any pump whose measured test parameters fall within the Code "Required Action Range" are immediately declared inoperable.
We  still  need four working days for performing a complete analysis of pump data per relief request PV-4.
C n
NRC REQUEST You requested    relief  from paragraph IWV-3411 for valves 63-525 and 63-526 and propose to exercise these valves during refueling to verify that they will  close. You must also verify that these valves      will perform their safety-related function by passing design flow from the SLCS to the core.
Please verify that this function will also be tested during refueling.
TVA RESPONSE We verify that valves 63-525 and -526 will perform their safety-related function by passing design flow from the SLCS to the core during refueling.
: 5. NRC REQUEST You  requested  relief  from paragraph IWV-3411  for valves 74-661 and -662 and propose    to exercise these valves at each refueling because such a test entails entry into containment. We approve this request with the condition that these valves also are tested during a cold shutdown whenever the containment is de-inerted.      Please pr ovide a commitment to perform tests during cold shutdown whenever possible (not to exceed thr ee months frequency) or provide justification for not commiting to this schedule.
TVA RESPONSE We do not believe the benefits of testing of valves 74-661 and -662 during cold shutdown warrant the increased risks to personnel safety. These risks include working and carrying test equipment in high radiation, high temperature, and poorly accessible areas. These risks were discussed in-detail with NRC at the May 1982 meetings at Browns Ferry.
: 6. NRC REQUEST From a  review of your IST program, the staff finds that you have elected to leak test pressure-isolation valves to verify integrity. It is the staff's position that,,when leak-rate testing is used to ve'rify the integrity of pressure isolation valves, the leakage limits selected must assure that valve sealing function has not excessively degraded. The staff does not consider relief valve capacity in setting pressure isolation valve 'leakage limits. The staff recommends a leakage limit for
    'pressure isolation valves of 0.5 gpm per nominal inch of valve size with a maximum leakage rate of 5 gpm. State whether you comply with this postion. If  you do not comply state and justify your acceptance test limits.
TVA RESPONSE We  do not'comply with the staff recommended limits. Our Section XI acceptance test limits for Pressure Isolation Valves (PIV) are based on system relief valve capacities, which are higher than the NRC staff recommended leakage limits. However, these valves are also tested in accordance with Appendix J and with reference leakage rate acceptance criteria that are more stringent than the recommended limits. Rather than a basis of unnecessarily limiting values our acceptance criteria were chosen considering the design funct'ion of these valves and their integrated system responses with the closed loop safety systems. In practice we easily meet the recommended limits while on the other hand we do not limit ourselves to PIV leakage rates that would be less than those needed to protect the system integrity.
: 7. NRC REQUEST Your IST program did not indicate performance  of position indicator verifications  as required by the Code. Please  verify that you meet this Code  requirement or  )ustify your failure to do so.
TVA RESPONSE We  do meet the Code requirement of position indication verifications. This request was made previously in a letter from D. B. Vassallo to H. G.. Parris dated January 17, 1983, and responded to in letter from L. M. Mills to H. R. Denton dated April 6, 1983.


NRC Letter from D.B.Vassallo to H.G.Parris dated February 10, 1984)NOTE: TVA's philosophy in writing the pump and valve testing program has been to include those systems and piping that carry water, steam, or radioactive material.We see no defined regulatory basis for the NRC staff to increase the scope of testing in the inservice pump and valve testing program, as is apparently the intent of questions 1 and 2.We, therefore, plan to respond only to those water, steam, or radioactive waste-containing components in questions land 2, and request that our submittals be reviewed against currently defined regulatory requirements.
1., NRC REQUEST The pump portion of the IST program was reviewed to verify that all pumps that are important to safety are included in the program and are subjected to the testing required by the ASME Code.In the staff's judgment there are additional systems wherein the associated pumps should be in the program.These systems are: Plant Service Water PSC Head Tank Fuel Oil Transfer Please justify the omission of the pumps in, these systems or revise the IST program to include them.TVA RESPONSE Plant Service Water Pumps--The plant service water system performs no safety-related function;hence, its pumps are not considered in the scope of Section XI.Pressure Suppression Chamber (PSC)Head Tank--The pumps in the Keep Fill system do not perform an active safety function in"keeping the core spray and RHR systems charged.The head tank water volume maintains these systems charged at the required pressure.The head tank pumps maintain the proper ahead tank level with occasional makeup to the head tank.Fuel Oil Transfer-See note above.
2.NRC REQUEST Likewise, in the staff's judgement the following valves should be in the IST program: Combustible Gas Control System valves Primary Containment Atmosphere valves Fuel Oil Transfer System valves Transverse In-Core Probe valves Valves in the portions of the Instrument and Control Air System that perform a function important to safety Valves in ventilating systems that perform a function important to safety Sampl'ing System valves Torus Drain Valves Drywell-Pressure Suppression Chamber (PSC)and PSC-Reactor Building vacuum breakers SRV discharge line vacuum br eakers (Valves 10-506, 507, 519, etc.)Primary Containment H2 and 02 Analyzer Valves EECM valves for the Unit 1 and 2 Diesel Generator Engine Coolers Diesel Generator Air Start Valves All relief valves important to safety except ADS valves (e.g., valves 75-543 A and B).Keep-Fill valves in Core Spray System (e.g., valves 75-609 and-610)Please provide technical justification for the omission of these valves or revise the IST program to include them.TVA RESPONSE Combustible Gas Control System Valves--See note above.I Primary Containment Atmosphere Valves--See note above.Fuel Oil Transfer System Valves--See note above.A Traversing In-Core Probe Valves-See note above.Valves in Instrument and Control Air System--See note above.I Valves in Ventilating Systems--See note above.Sampling System Valves-The sampling system valves (43-13, 14, 28A, 28B, 29A, and 29B), which perform a containment isolation function and are tested, in accordance with the criteria in Appendix J, are identified as Clas's A valves and included in Attachment 3 of the pump and valve program.
0 r Torus Drain Valves-The torus drain valves (75-57, 58)that perform a containment isolation function are included in the program.Drywell-PSC and PSC-Reactor Building Vacuum Breakers--See note above.SRV Discharge Line Vacuum Breakers--See note above.Primary Containment H2 and 02 Analyzer Valves--See note above.EECW Valves for units 1 and 2 Diesel Generator Engine Coolers--These valves are tested per Section XI requirements but were inadvertently left out of the program submittal.
They are included in the updated program.Diesel Generator Air Start Valves--See note above.All Relief Valves Important to Safety--We have reviewed the various safety systems and have included those relief valves determined to be needed in our program.Keep Fill Valves in Core Spray and RHR Systems-These valves have been included in the progr am as indicated in the valve listing with the conditions noted in Request for Relief PV-12.3.NRC REQUEST You requested relief for all pumps from the requirements of paragraph IWP-3220 that all pump test data be analyzed within 96 hours after completion of the test.We agree that a delay of an additional day before pump test data is completely analyzed is not significant if there is no delay in performing preliminary reviews of test data (including vibration levels)immediately after the test, and any pumps whose measured test parameters fall within the Code"Required Action Range" are immediately declared inoperable upon completion of the preliminary reviews.Confirm that this is your intent.TVA RESPONSE A preliminary analysis is performed on pump test data (including vibration) immediately after the test.Any pump whose measured test parameters fall within the Code"Required Action Range" are immediately declared inoperable.
We still need four working days for performing a complete analysis of pump data per relief request PV-4.
C n NRC REQUEST You requested relief from paragraph IWV-3411 for valves 63-525 and 63-526 and propose to exercise these valves during refueling to verify that they will close.You must also verify that these valves will perform their safety-related function by passing design flow from the SLCS to the core.Please verify that this function will also be tested during refueling.
TVA RESPONSE We verify that valves 63-525 and-526 will perform their safety-related function by passing design flow from the SLCS to the core during refueling.
5.NRC REQUEST You requested relief from paragraph IWV-3411 for valves 74-661 and-662 and propose to exercise these valves at each refueling because such a test entails entry into containment.
We approve this request with the condition that these valves also are tested during a cold shutdown whenever the containment is de-inerted.
Please pr ovide a commitment to perform tests during cold shutdown whenever possible (not to exceed thr ee months frequency) or provide justification for not commiting to this schedule.TVA RESPONSE We do not believe the benefits of testing of valves 74-661 and-662 during cold shutdown warrant the increased risks to personnel safety.These risks include working and carrying test equipment in high radiation, high temperature, and poorly accessible areas.These risks were discussed in-detail with NRC at the May 1982 meetings at Browns Ferry.6.NRC REQUEST From a review of your IST program, the staff finds that you have elected to leak test pressure-isolation valves to verify integrity.
It is the staff's position that,,when leak-rate testing is used to ve'rify the integrity of pressure isolation valves, the leakage limits selected must assure that valve sealing function has not excessively degraded.The staff does not consider relief valve capacity in setting pressure isolation valve'leakage limits.The staff recommends a leakage limit for'pressure isolation valves of 0.5 gpm per nominal inch of valve size with a maximum leakage rate of 5 gpm.State whether you comply with this postion.If you do not comply state and justify your acceptance test limits.
TVA RESPONSE We do not'comply with the staff recommended limits.Our Section XI acceptance test limits for Pressure Isolation Valves (PIV)are based on system relief valve capacities, which are higher than the NRC staff recommended leakage limits.However, these valves are also tested in accordance with Appendix J and with reference leakage rate acceptance criteria that are more stringent than the recommended limits.Rather than a basis of unnecessarily limiting values our acceptance criteria were chosen considering the design funct'ion of these valves and their integrated system responses with the closed loop safety systems.In practice we easily meet the recommended limits while on the other hand we do not limit ourselves to PIV leakage rates that would be less than those needed to protect the system integrity.
7.NRC REQUEST Your IST program did not indicate performance of position indicator verifications as required by the Code.Please verify that you meet this Code requirement or)ustify your failure to do so.TVA RESPONSE We do meet the Code requirement of position indication verifications.
This request was made previously in a letter from D.B.Vassallo to H.G..Parris dated January 17, 1983, and responded to in letter from L.M.Mills to H.R.Denton dated April 6, 1983.
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Revision as of 01:56, 22 October 2019

Responds to 840210 Request for Addl Info Re Proposed Inservice Pump & Valve Testing Program.Revised Program Encl, Including Requests for Relief from Certain ASME Requirements.Program Supersedes 820831 Program
ML18029A163
Person / Time
Site: Browns Ferry  Tennessee Valley Authority icon.png
Issue date: 10/01/1984
From: Mills L
TENNESSEE VALLEY AUTHORITY
To: Harold Denton
Office of Nuclear Reactor Regulation
References
NUDOCS 8410110067
Download: ML18029A163 (54)
v • d • e


Text

REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCE.S5lON NBR:8410110067 OC DATE: 84/10/01 NOTARI D: YES DOCKET FACIL:50-259 Browns Ferry Nuclear Power Stationi Unit li Tennessee 05000259 50-260 Browns Ferry Nuclear Power Stations Unit 2< Tennessee 05000260 50-296 Browns Ferry Nuclear Power 'Stations Unit 3< Tennessee 05000296 AUTH. NAME AUTHOR AFFILIATION MILLS L,M>>

g Tennessee Valley Authority RECIP NAME

~ RECIPIENT AFFILIATION DENTONgH ~ RE Office of Nuclear Reactor Regulationi Director

SUBJECT:

Responds to 800210 request for addi info re proposed inser vice pump 8 valve testing program. Revised program encl/

including requests for relief from certain ASME requirements, Program supersedes 820831 program, DISTRIBUTION CODE: A047D COPIES RECEIVED:LTR ENCL SIZE; TITLE."OR Submittal: Inservice Inspection/Testing NOTES:NMSS/FCAF 1cy. 1cy 05000?59 NMSS/FCAF/PM'L:06/26/73 NMSS/FCAF 1cy, 1cy 05000260 NMSS/FCAF/PM'L:06/28/7q NMSS/FCAF 1cy. 1cy 05000296 NMSS/FCAF/PM'Lo07/0?/76 RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL NRR ORB2 BC 01 7 7 INTERNAL: ADM/LFMB 1 0 ELD/HDSO NRR/DE/MEB 15 1 1 gg/ MTEB 14 NRR/DL/TAPMG 1 1 rRE'G FIL 04 RGN2 1 1 EXTERNAL: ACRS 16 10 10 LPDR 03 NRC PDR 02 1 1 NSIC 05 NTIS 1 1 NOTES; TOTAL NUMBER OF COPIES REQUIRED! LTTR 30 ENCL 28

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TENNESSEE VALLEY AUTHORITY cHATTANooGA. TENNEssEE 37401 400,Chestnut 'Street"Tower II October 1, 1984 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555

Dear Denton:

In the Matter of the Docket Nos. 50-259 Tennessee Valley Authority 50-260 50-296 By my letter to you dated August 31, 1982, we submitted for your staff's review the proposed Inservice Pump and Valve Testing Program for the Browns Ferry Nuclear Plant units 1, 2, and 3. In response to your staff's request;, additional information was submitted by my letter to you dated April 6, 1983.

I A request for additional information was transmitted to TVA by letter from D. B. Vassallo to H. G. Parris dated February 10, 1984. In response to that request, we have revised the program provided as enclosure 1.

Included are requests for relief from certain Code requirements. None of the changes reflect a relaxation of test procedures. Specific responses to each of the requests made in the February 10, 1984 letter is provided in enclosure 2.

The revised Inservice Pump and Valve Testing Program for Browns Ferry provided as enclosure 1, supersedes the program submitted by my letter to you dated August 31, 1982.

If you have any questions, please get in touch with us through the Browns Ferry Project Manager.

Very truly yours, TENNESSEE VALLEY AUTHORITY c

d L. M. Mills, Manager Nuclear Licensing Sworn to .ng subscribe befo e me th s 'M day of 1984.

Notar y Public My Commission Expires Enclosures cc: See page 2 84iOii0067 84100i

"PDR ADOCK 05000259 P PDR An Equal Opportunity Employer

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Mr. Harold R. Denton October 1, 1984 cc (Enclosures):

U.S. Nuclear Regulatory Commission Region II ATTN: James P. O'Reilly, Regional Administrator 101 Marietta Street, Suite 2900 Atlanta, Georgia 30323 Mr. R. J. Clark Browns Ferry Project Manager U.S. Nuclear Regulatory Commission 7920 Norfolk Avenue Bethesda, Maryland 20814 Mr. E. H. Girard U.S. Nuclear Regulatory Commission Region II 101 Marietta Street, Suite 2900 Atlanta, Georgia 30323

1 ENCLOSURE 1 ASME SECTION XI INSERVICE PUMP AND VALVE TESTING PROGRAM BROMNS FERRY NUCLEAR PLANT UNITS 1, 2, AND 3 (DOCKET NOS. 50-259, -260, -296) : Inservice Testing Program for ASME Code Classes 1, 2, and 3 Pumps : Valves to be Cycled for ASME Section XI (IWV-3410, 3510, 3520, and 3610) : Category A Valves and Testing Criteria (Appendix J, Secti'on XI, or both) : Requests for Relief

AXiKP29K 1 1 ~

ItJSERVICE leSTIN'i PKCP~uk FOR AS c.

CODE CLASSES 1, 2, AtJD 3 PU."'PS The following table provide" a tabulation of pmps that are subjec'c t'.e testing requirements of Sub"ecticn IMP of Section XI of the I~YZ J.'w ler and Pressur": Vessel Code, 1980 Edi'icn, and Add nda thrcugh Hinter 19tC. Thi s

p. ograrn will be applicable until August 31, 1992.

This tabulation identifies the pcnps to be tes'ed, pup code classes, pararne'ers to be rneasur ed, and test irtervals.

H~ Ma~ 3 Zi Z J ~n 2 NR Q 0 Q tJA 0 NR HPCI. 2 Q Q Q 0 tJA ~ 0 0 RCIC 2 Q 0 Q 0 tJA 0 0<

Core Spray JJR Q Q Q tJA Q JJR Standby Liquid Control '2 2 lJR JR Q Q 'JA Q RFIRS( 1 ) 3 tJR Q Q Q tJA' !JR Rotative Lor Lubricant Level or Pressur" P'ifferential H

Pi Speed Inlet Pres ure Pressr:r e tJR tJA P

tarot tJo Required Avail able Qi Flow Rate H Mcntrg y Tb Bearir:g Temperature Q Quarterly V Vibraticrr Anrpl i tude A Annually (1) These punps are ir a systerr ccexnon to units 1, 2, and 3. Ability to start the pumps will be derncnstrated frcrn each control roan, but canparison to baseline parameters of vibraticn, flew rate, and differential pressure will be perfcrrned for instrumentation in unit 3 only, for ccnsistency of d'ata.

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The following table provides a listing of systems, valve numbers, types, categories, test frequencies, and type of tests for those valves to be I

cycled in accordance with ASME Section XI, IHV-3410, 3510, 3520, and 3610.

4

TEST XLQD'. HKQXH<Y Main Steam 1-14 A Q Full Cycle 1-15 A Q Full Cycle 1-26 A Q Full Cycle 1-27 A Q Full Cycle 1-37 A Q Full Cycle 1-38 A Q Full Cycle 1-51 A Q Full Cycle 1-52 A Q Full Cycle Main Steam 1-4 C 60 months Meets IWV-3510 (Rel'ief Valves) 1-5 C 60 months Meets IWV-3510 1-18 C 60 months Meets'IWV-3510 1-19 C 60 months Meets IWV-3510 1-22 C 60 months Meets IWV-3510 1-23 C 60 months Meets IWV-3510 1-30 C 60 months Meets IWV-3510 1-31 C 60 months Meets IWV-3510 1-34 C 60 months Meets IWV-3510 1-41 C 60 months Meets IWV-3510 1-42 C 60 months Meets IWV-3510 1-179 C 60 months Meets Mf-3510 1-180 C 60 months Meets IWV-3510 Feedwater (Check Valves) 3-554 AC Operating Cycle Full Cycle, PV-8 3-558 AC Operating Cycle Full Cycle, PV-8 3-568 AC Operating Cycle Full Cycle, PV-8 3-572 AC Operating Cycle Full Cycle, PV-8 23-34 Full Cycle 23-40 -

Full Cycle 23-46 Full Cycle 23-52 Full Cycle 23-57 ( U-142) Full Cycle RHRSW

,(Check Valves)23-502 C Q Full Cycle 23-506 C Q Full, Cycle 23-522 C Q Full Cycle 23-526 C Q Full Cycle 23-542 C Q Full Cycle 23-546 C Q Full Cycle 23-561 C Q Full Cycle 23-565 C Q Full Cycle 23-579 (510 U1) C Q Full Cycle 23-580 (530 U1) C Q Full Cycle 23-581 (550 U1) C Q Full Cycle 23-582 (569 U1) C Q Full Cycle 23-591 C Q Full Cycle 23-594 C Q - Full Cycle 23-597 C Q Full Cycle 23-588 C Q Full Cycle

TEST

~Y~gM MCXKQBX GKQUKKX P OF SLC 63-514 C Q Full Cycle (Check Valves)63-516 C Q Full Cycle 63-525 AC Operating Cycle Full Cycle, PV-8 63-526 AC Operating Cycle Full Cycle, PV-8 SLC 63-512 Operating Cycle Tech Spec 4.4.A.2 (Relief Valves)63-513 Operating Cycle Tech Spec 4.4.A.2 SLC (Explosive 63-SA 2-year Cycle IWV-3610 Valves) 63-SB 2-year Cycle 1WV-3610 EE% 67-13 Full Cycle 67-14 Full. Cycle 67-17 Full Cycle 67-18 Full Cycle 67-21 Full Cycle 67-22 Full Cycle 67-25 Full Cycle 67-26 Full Cycle 67-48 Full Cycle 67-49 Full Cycle EEL 67-502 C Q Part Cycle, PV-,10 (Check Valves)67-582 C Q Part Cycle, PV-10 67-622 C Q Part Cycle, PV-10 67-619 C Q Part Cycle, PV-10 67-541 C Q Part Cycle, PV-10 67-542 C Q Part Cycle, PV-.10 67-584 C Q Part Cycle, PV-10 67-585 C Q Part Cycle, PV-10 67-648 C Q Part Cycle, PV-10 67-649 C Q Part Cycle, PV-10 67-656 C Q Part Cycle, PV-10 67-657 Q Part Cycle, PV-10 67-559 Q Part Cycle, PV-10 67>>558 Q Part Cycle, PV-10 67-638 Q Part Cycle, PV-10 67<39 Q Part Cycle, PV-10 67-600 Q Part Cycle, PV-10 67-601 Q Part Cycle, PV-10 67-659 Q Part Cycle, PV-10 67-660 Q Part Cycle, PV-10 67-556 Q Part Cycle, PV-10 67-598 Q Part Cycle, PV-10 67693 (U-3) Q Part Cycle, PV-10 67-694 (U-3) Q Part Cycle, PV-10 67%95 (U-3) Q Part Cycle, PV-10 67-696 (U-3) Q Part Cycle, PV-10 67-705 (U-3) Q Part Cycle, PV-10 67-706 (U-3) Q Part Cycle, PV-10 67-703 (U-3) Q Part Cycle, PV-10 67-704 (U-3) Q Part Cycle, PV-10

TEST KQBX ZEK8LKKX EECM 67-528 (U-1) C Q Part Cycle, PV-10 (Check Valves67-529 (U-1) C Q Part Cycle, PV-10

-

Continued) 67%34 (U-1) C Q Part Cycle, PV-10 67%35 (U-1) C Q Part Cycle, PV-10 67-521 (U-1) C Q Part Cycle,. PV-10 67-522 (U-1) C Q Part Cycle, PV-10 67-630 (U-1) C Q Part Cycle, PV-10 67-631 (U-1) C Q Part Cycle, PV-10 67-624 (U>>1) C Q Part Cycle, PV-10 67-625 (U-1) C Q Part Cycle, PV-10 67-514 (U-1) C Q Part Cycle, PV-10 67-515 (U-1) C Q Part Cycle, PV-10 67-627 (U-1) C Q Part Cycle, PV-10 67-628 (U-1) C Q Part Cycle, PV-10 67-507 (U-1) C Q Part Cycle, PV-10 67-508 (U-1) C Q Part Cycle, PV-10 67-838 C Q ,Part Cycle, PV-10 67-839 C Q Part Cycle, PV-10 67-843 C Q Part Cycle, PV-10 67-844 C Q Part Cycle, PV-10 67-715 (U-3) Q Part Cycle, PV-10 67-716 (U-3) Q Part Cycle, PV-10 67-713 (U-3) Q Part Cycle, PV-10 67-714 (U-3) Q Part Cycle, PV-10 67-723 (U-3) Q Part Cycle, PV-10 67-724 (U-3) Q Part Cycle, PV-10 67-725 (U-3) Q Part Cycle, PV-10 67-726 (U-3) Q Part Cycle, PV-10 67-737 (U-,3) Q Part Cycle, PV-10 67-738 (U-3) Q Part Cycle, PV-10 67-735 (U-3) Q Part Cycle, PV-10 67-736 (U-3) Q Part Cycle, PV-10

TEST

~CKBX HMlKhLCX Recirculation 68-3 Cold Shutdown Full Cycle Loops 68-79 Cold Shutdown Full Cycle Recirculation 68-508 AC Operating Cycle Full Cycle, PV-8 Loops68-523 AC Operating Cycle Full Cycle, PV-8 (Check Valves)68-550 AC Operating Cycle Full Cycle, PV-8 68-555 AC Operating Cycle Full Cycle, PV-8 RWCU 69-1 Full Cycle 69-2 Full Cycle RWCU 69-579 -AC Operating Cycle Full Cycle, PV-8 (Check Valves)69-624 (U-3) AC Operating Cycle Full Cycle, PV-8 RCIC 71-2 A Cold Shutdown Full Cycle 71-3 A Cold Shutdown Full Cycle 71-5 B Q Full Cycle 71-6A B Q Full Cycle

,71-6B B Q Full Cycle 71-34 B Q Full Cycle 71-8 B Q Full Cycle 71-9 B Q Full Cycle 71-10 B Q Full Cycle 71-17 B Q Full Cycle 71-18 B Q Full Cycle 71-25 B Q Full Cycle 71-37 B Cold Shutdown Full Cycle 71-39 A Cold Shutdown Full Cycle 71-40 AC Cold Shutdown Full Cycle 71-22 B Q Full Cycle RCIC 71-580 AC Q Full Cycle (Check Valves)71-597 C Q Full Cycle, PV-11 71-598 C Q Full Cycle, PV-11 71-599 C Q Full Cycle, PV-11 71-600 C Q Full Cycle, PV-11 71-508 C Operating Cycle Internal Inspection, PV-9 71-592 AC Q Full Cycle, PV-11 RCIC 71-543 60 Months Meets IWV-3510 (Relief Valves)71-503 60 months Meets IWV-3510 HPCI 73-81 Cold Shutdown Full Cycle 73-2 Cold Shutdown Full Cycle 73-3 Cold Shutdown Full Cycle 73-5 Q Full Cycle

TEST MCZKEK ZlKQL~~Y HPCI ~

73-6A B Q Full Cycle (Continued) 73-6B B Q Full Cycle 73-16 B Q Full Cycle 73-18 B Q Full Cycle 73-19 B Q Full Cycle 73-26 B Q Full Cycle 73-27 B Q Full Cycle 73-34 B Cold Shutdown Full Cycle 73-43 B Q Full Cycle 73 44 A Cold Shutdown Full Cycle

'73-45 AC Cold Shutdown Full Cycle 73-30 B Q Full Cycle HPCI 73-574 60 Months Meets IHV-3510 (Relief Valves)73-506 60 Months Meets IHV-3510 73-559 C Q Full Cycle HPCI 73-517 C Operating Cycle Internal Inspection, PV-9 (Check Valves)73-603 AC Q Full Cycle 73-609 AC Q Full Cycle 73-633 C Q Full Cycle, PV-11 73-634 C Q Full Cycle, PV-11 73-635 C Q Full Cycle, PV-11 73-636 C Q Full Cycle, PV-11 RHR 74-1 B Q Full Cycle 74-2 B Q Full Cycle 74-7 B Q Full Cycle 74-12 B Q Full Cycle 74-13 B Q Full Cycle 74-24 B Q Full Cycle 74-25 B Q Full Cycle 74-30 B Q Full Cycle 74-35 B Q Full Cycle 74-36 B Q Full Cycle 74 47 A Cold Shutdown Full Cycle 74-48 A Cold Shutdown Full Cycle 74-52 B Q Full Cycle 74-53 A Cold Shutdown Full Cycle 74 54 AC Cold Shutdown Full Cycle 74-57 A Q Full Cycle 74-58 A Q Full Cycle, 74-59 B Q Full Cycle 74-60 A Q Full Cycle 74-61 A Q. Full Cycle 74-66 B 'Q Full Cycle 74-67 A Cold Shutdown Full Cycle 74-68 AC Cold Shutdown Full Cycle

TEST

. ~GAL ZBKKFJLX 74-.71 A Q Full Cycle 74-72 A Q Full Cycle 74-73 B Q Full Cycle 74 74 A Q Full Cycle 74-75 A Q Full Cycle 74-77 A Cold Shutdown Full Cycle 74-78 A Cold Shutdown Full Cycle 74-96 B Q Full Cycle 74-97 B Q Full Cycle 74-100 (U-28 3) B Q Full Cycle 74-101 (U-18 2) B Q Full Cycle 74-98 B Q Full Cycle 74-99 B Q Full Cycle RHR 74-686 60 Months Meets IWV-3510 (Relief Valves) 74-509A 60 Months Meets IWV-3510 74-509B 60 Months Meets IWV-3510 74-509C 60 Months Meets IWV-3510 74-509D 60 Months Meets IWV-3510 74-587A 60 Months Meets IWV-3510 74-587B 60 Months Meets IWV-3510 74-659 60 Months Meets IWV-3510 RHR 74-559A C Q Full Cycle (Check Valves) 74-559B C Q Full Cycle 74-559C C Q Full Cycle.

74-559D C Q Full Cycle 74-661 AC Operating Cycle Full Cycle, PV-8 74-662 AC Operating Cycle Full Cycle, PV-8 74-560A C Q Full Cycle 74-5608 C Q Full Cycle 74<<560C C Q Full Cycle 74-560D C Q Full Cycle 74-792 C Q Full Cycle, PV-12 74-804 C Q Full Cycle, PV-12 74-802 C Q Full Cycle, PV-12 74-803 C Q Full Cycle, PV-12 Core Spray 75-2 B Q Full Cycle 75-9 B Q Full Cycle 75-11 B Q Full Cycle 75-22 B Q Full Cycle 75-23 B Q ~

Full Cycle 75-25 A Cold Shutdown Full Cycle 75-26 AC Cold Shutdown Full Cycle 75-30 B Q Full Cycle 75-37 B Q Full Cycle

TEST

)LEAK QKKQQBX GEQXKK Core Spray 75-39 B Q Full Cycle (Continued) 75-50 B Q Full Cycle 75-51 B Q Full Cycle 75-53 A Cold Shutdown <<

Full Cycle 75-54 AC Cold Shutdown Full Cycle 75-57 A Q Full Cycle 75-58 A Q Full Cycle Core Spray 75-537A C Q Full Cycle (Check Valve) 75-537B C Q Full Cycle 75-537C C Q Full Cycle 75-537D C Q Full Cycle 75-570A C Q Full Cycle 75-570B C Q Full Cycle 75-570C C .Q Full Cycle 75-570D C Q Full Cycle 75-606 C Full Cycle, PV-12 75-607 C Full Cycle, PV-12 75-609 C Q Full Cycle, PV-12 75-610 C Q Full Cycle, PV-12 Core Spray 75-507A C 60 Months Meets IWV-3510 (Relief Valves) 75-507B C 60 Mont;hs Meets IWV-3510 75-507C C 60 Mont;hs Meets IWV-3510 75-507D C 60 Mont;hs Meets IWV-3510 75-543A C 60 Months Meets IWV-3510 75-543B C 60 Months Meets IWV-3510 Floor and 77-2A A Q Full Cycle Equipment 77-2B A Q Full Cycle, Drains77-15A A Q Full Cycle 77-15B A Q Full Cycle CRD Hydraulic 85-39A-(1-185) B B 10$ of valves Full Cycle 85-39B-( 1-185) B B every 16 weeks, Full Cycle 1

valves also cycle during any unit scram, all valves also tested each refueling outage Notes:

1. Valve position indication checks are performed per the code,
2. This program is in accordance with Subsection IWV of the 1980 edition through Winter 1980 Addenda of Section XI and is applicable through August 31, 1992.

'

This table identifies the Category A valves, and the testing criteria

, 'Appendix J,Section XI, or both) to be satisfied at each refueling outage.

Testing criteria is based on Items 2, 3, and 4 of t'n '

nts

, attached to NRC (T.A. Ippolito) letter to TVA (N. B.

Hughes) of August 8, 1978.

ed' 1-14 X 1-15 X 1-26 X 1-27 X 1-37 X 1-38 X 1-51 X 1-52 X 1-55 X 1-56 X 3-554 X 3-558 X 3-568 X 3-572 X 43-13 X 43-14 X

'3-28A X

43-28B X 43-29A X 43-29B X 63-525 X 63-526 X 68-5o8 X 68-523 X 68-55O X 68-555 X 69-1 X 69-2 X 69-579 X 69-624 (Unit 3) X 71-2 X 71-3 X

0 n C M c'n I 71-39 X 71-40 X 71-14 X 71-32 X 71-580 X 71-592 X

Yale.~~ ASM c 73-2 X 73-3 X 73-81 X 73-44 X 73-45 X 73-23 X 73-24 X 73-603 X 73-609 X 74 47 X X 74-48 X X 74-53 X X 74-54 X X 74-57 X 74-58 X 74-60. X 74-61 X 74-67 X X 74-68 X X.

74-71 X 74-72 X 74 74 X

'74-75 X

'4-77 X X 74-78 X X 74-661 X' X

'74-662 X, 75-25 X X 75-26 X X 75-53 X X 75-54 X X 75-57 X 75<<58 X 77-2A X 77-2B X 77-15A X 77-15B X

C M REQUEST FOR RELIEF

LI P

~CM Qg~S - RHR Pumps A, B, C, D; HPCI Pump; RCIC Pump; Core Spray, Pumps A, B, C, D; SLC Pumps A, B; RHRSM Pumps A1, A2, A3). B1 ~ B2~ B3~ C1 ~ C2~ C3~ D1 ~ D2~ D3

~CA~) - Class 2, except RHRSW Pumps which are Class 3.

QUQCCggg - ECCS and Core Heat Removal (RHRSM Pumps).

- Monitoring bearing temperatures during quarterly inservice testing.

Bh@MRE

- All of these pumps, except HPCI and RCIC, have water lubricated pump bearings. The RHR, Core Spray, SLC, and RHRSW pump bearings are lubricated by water supplied by the pump itself.

Satisfactory pump operation is indicative of sufficient bearing lubrication. HPCI and RCIC have oil cooled bearings, but these pumps cannot be operated long enough to reach stable bearing temperatures without overheating the torus and causing plant shutdown. The HPCI bearings, which are instrumented, are monitored during testing. RCIC bearings do not have temperature instrumentation.

4 LLZKBHKK Vibration measurements are taken on all of the Section XI pumps to ensure detection and correction of changes in bearing performance while the pumps are still capable of .satisfactory operation.

Standby Liquid Control Pumps

- Class 2 ECCS and alternate reactor shutdown capability'.

Quarterly measurement of inlet pressure and differential pressure.

- During testing these pumps take suction from a test tank that has a relatively small range of level variation during pump operation. In addition, these are positive displacement pumps whose inlet pressure does not affect pump operating characteristics. Therefore, differential pressure measurement is not important.

Pump

, discharge pressure will be measured during quarterly testing. A caution note has been placed in the instruction that governs this test so that a minimum level is maintained in the test tank. This ensures discharge pressure is an adequate indication of pump performance.

~C~P~NT Standby Liquid Control Pumps

~CPS . - Class 2 f~CJQg - ECCS.and alternate reactor shutdown capability.

L Running pumps for five'minutes before measuring parameters.

~3~/

XK42Z - These pumps are tested by circulating liquid to a test tank for.

2 minutes and measuring the volume change in the tank. Running for 5 minutes before measuring parameters is not compatible with the system design. However, a 15-minute functional test which involves recirculating water back to the test tank is run before the system is lined up for the Section XI test require-ment. This 15-minute test is of sufficient length for all parameters to stabilize and the 2-minute test is run immediately afterward.

ZRXXK Measure parameters during 2-minute test.

C 4

IJ

L

- All systems

- Analysis of test data within 96-hours per 1WP 3220.

B~~S

. I~LI 'F - Due to the time involved in processing surveillance instructions to the reviewer and the possibility of weekends and/or holidays falling between running tests and completely reviewing the results, 96-hours is impractical.

Pump parameters of flow rate and differential pressure will be reviewed imnediately after the test by the individual performing the test to verify that they do not fall within the "Required Action Range>> of Table IWP-3100-2. Complete analysis of test data will be performed within 4 working days of the tests. Xf the pump parameters fall within the "Required Action Range," the individual performing the test will notify the cognizant reviewer and carry out the necessary action required .

by the code.

~C pgg5XQ Installed plant instrumentation and portable instruments used to measure pump parameters.

Q~>S -1,2,and3 QJ~CI~O Measurement of pump parameters.

Instrunent accuracy shall be within the limits of'Table IMP-4100-1.

- The accuracy of installed plant indicators is ~2'5 of full scale. However, the accuracy of installed transmitters and square-rooters is 0.5$ and when these are taken into account the instrument loop accuracies are 2.5$ and 3.0$ for pressure loops and flow loops, respectively. The plant installed instr+vents will continue to be used since any alternate method such as connecting test instrunents into the system or* .

replacing plant instrumentation, will not provide sufficient benefit to outweigh the added'cost and manpower of the alternate methods.

The portable instrument used to measure vibration amplitude has an accuracy of 11% of full scale. The instrunent has been used from the beginning of the program to collect the vibration data and develop all the vibration baselines that are used in the pump program. Since all other requirements for measuring amplitude (XWP-4520) have been met and since the instrunent used is an accepted standard method for industrial, vibration and measurements, the instrunent will continue to be used.

XFAGHG An equipment diagnostic program using much more sophisticated instrunents and methods monitors rotating equipment at the plant and provides much better vibration data on the pumps than the one required data point of the pump program. This program is done in addition to the test requirement.

S LI F

- All valves

- A, B, and C

-, Various functions Corrective action on an inoperable valve required before startup per Mf-3417 and IWV-3523.

- Limiting conditions for startup have been analyzed in Browns Ferry Technical Specifications, Technical Bases 3.4.B, 4.4, 3 O'As 3'5 't 3 O'Ct 3'O'Es 3'5 F

.

Valve 'inoperability will preclude unit startup only if the valve places the system itself in a position of preventing startup per present technical specifications.

fl L P CRD (Scram Function) 39A (1-185)85-39B -. (1-185)

- Provide flow path for water for control rod scrams.

Exercised once every 3 months.

Cycling these valves requires scramming a control rod. There are 185 control rods in the reactor. Scramming every rod once every three months is not practical for the following reasons.

a. A power reduction is required to test the scram function.

Reducing power for the length of time required to scram 185 rods places an unfair burden on the licensee.

b.'uel preconditioning must follow this power reduction to avoid possible fuel damage. The longer the reduction in power, the longer the pr'econditioning.

10$ of the rods will be scram testd every sixteen weeks, and all rods will be scram tested during refueling, per present Technical Specifications. Xn addition, all rods are provided with the same test during normal operation when the unit scrams.

lt LlE

&5XF85L MCHRQHlBG5 Feedwater 3-554, 3-558, 3-568, 3 572 (VALVES) Standby Liquid Control 525,63-526 Reactor Recircultion System 68-508, 68-523,68-550, 68-555 Reactor Water Cleanup 579,69-624 (Unit 3 only)

Residual Heat Removal 661,74-662

- AC ZEKTXQH - All are containment isolation, plus; prevents backflow in feedwater lines (System 3), prevents backflow in RWCU System (System 69), and thermal expansion relief (System 74).

- Exercise valves for operability quarterly.

~ASS QQ jgL:gF All of these valves are check valves whose operation cannot be verified during plant operation. Testing requires entry into primary containment, stopping RWCU system operation (System 69) or inter rupting seal water to the recirculation pumps (System 68) which is very likely to cause seal damage.

Valves74-661, 662 are not required to change position and hence, are not required to be tested for operability.

~BHbXI'.

Valves will be tested in accordance with 10 CFR 50, Appendix J, at each refueling outage.

L

~XIZQL QZEQHKHX5 Reactor Core Isolation Cooling 508 (VALVES) High Pressure Coolant Injection 73-517 ZUK<UQH - Valves present backflow to the torus from the RCIC and HPCI, respectively.

- Valves cannot be cycled without introducing torus water into the vessel. This water is of such quality that it should not be introduced into the vessel unless an accident has occurred.

XLZ2583X Valve internals will be visually and manually checked each refueling outage by removal of valve access plates. Testing check valves each refueling outage is in line with the'RC's latest philosophy on testing check valves.

~Y~M MCKQKHXQ 502, 582, 622, 619 (VALVES)67-648, 649, 541, 542, 558, 559, 638, 639, 659, 657 656, 584, 585, 556, 598, 600, 601, 660, 659, 838, 839, 843, 844 1-67-634, 635, 528, 529, 521, 522, 630, 631, 624, 625, 514, 515, 627, 628, 507, 508 3-67-723, 724, 725, 726, 713, 714, 715, 716, 703, 704, 705, 706, 695, 696, 693, 694 3-67-735, 736, 737, 738 j~UC 'Igg - All required to pass rated flow to emergency coolers, plus backseat upon loss of one of the two EEL headers (except 3-67-735, 736, 737, '738 and 67-838, 839, 843, 844)

Operability test quarterly

- Backflow testing these valves individually cannot be performed due to lack of test connections between valves.

WXQEKTK These valves will be part stroke-tested quarterly (except 3 3XGX3¹ 735, 736, 737, 738) and an internal inspection done each.

refueling outage.

- High Pressure Coolant Injection 73-633, 634, 635, 636 Reactor Core Isolation Cooling 597, 598, 599) 600

- HPCI/RCIC Turbine Exhaust Vacuum Relief Exercise each valve for operability quarterly

- Each valve cannot be checked individually due to lack of isolation valves. The four valves are in a "one-out-of

-two-taken twice" arrangement, so there is redundancy in case a valve fails to open.

- Test each arrangement of valves quarterly.

It

'I

REQUEST FOR RELIEF - PV-12 MCHKHKHXQ - Core Spray 609, 610 75-606, 607 792, 804 74-802, 803 Prevents backflow into the keep fill system (PSC Head Tank)

XIX, Exercise each valve for operability quarterly ZKU~IE - Each individual valve cannot be tested due to lack of test connections.

L4TQ5hXK 3XSLQKi Quarterly testing of pairs of valves together plus an internal inspection each refueling outage.

'(

dl

ENCLOSURE 2 RESPONSE TO NRC REQUEST FOR ADDITIONAL INFORMATION REGARDING INSERVICE PUMP AND VALVE TESTING PROGRAM BROWNS FERRY NUCLEAR PLANT UNITS 1, 2, AND 3

(

Reference:

NRC Letter from D. B. Vassallo to H. G. Parris dated February 10, 1984)

NOTE: TVA's philosophy in writing the pump and valve testing program has been to include those systems and piping that carry water, steam, or radioactive material. We see no defined regulatory basis for the NRC staff to increase the scope of testing in the inservice pump and valve testing program, as is apparently the intent of questions 1 and 2. We, therefore, plan to respond only to those water, steam, or radioactive waste-containing components in questions land 2, and request that our submittals be reviewed against currently defined regulatory requirements.

1. , NRC REQUEST The pump portion of the IST program was reviewed to verify that all pumps that are important to safety are included in the program and are subjected to the testing required by the ASME Code. In the staff's judgment there are additional systems wherein the associated pumps should be in the program. These systems are:

Plant Service Water PSC Head Tank Fuel Oil Transfer Please justify the omission of the pumps in, these systems or revise the IST program to include them.

TVA RESPONSE Plant Service Water Pumps--The plant service water system performs no safety-related function; hence, its pumps are not considered in the scope of Section XI.

Pressure Suppression Chamber (PSC) Head Tank--The pumps in the Keep Fill system do not perform an active safety function in "keeping the core spray and RHR systems charged. The head tank water volume maintains these systems charged at the required pressure. The head tank pumps maintain the proper ahead tank level with occasional makeup to the head tank.

Fuel Oil Transfer See note above.

2. NRC REQUEST Likewise, in the staff's judgement the following valves should be in the IST program:

Combustible Gas Control System valves Primary Containment Atmosphere valves Fuel Oil Transfer System valves Transverse In-Core Probe valves Valves in the portions of the Instrument and Control Air System that perform a function important to safety Valves in ventilating systems that perform a function important to safety Sampl'ing System valves Torus Drain Valves Drywell - Pressure Suppression Chamber (PSC) and PSC Reactor Building vacuum breakers SRV discharge line vacuum br eakers (Valves10-506, 507, 519, etc.)

Primary Containment H2 and 02 Analyzer Valves EECM valves for the Unit 1 and 2 Diesel Generator Engine Coolers Diesel Generator Air Start Valves All relief valves important to safety except ADS valves (e.g.,

valves75-543 A and B)

. Keep-Fill valves in Core Spray System (e.g., valves75-609 and -610)

Please provide technical justification for the omission of these valves or revise the IST program to include them.

TVA RESPONSE Combustible Gas Control System Valves--See note above.

I Primary Containment Atmosphere Valves--See note above.

Fuel Oil Transfer System Valves--See note above.

Traversing In-Core Probe Valves A

See note above.

Valves in Instrument and Control Air System--See note above.

I Valves in Ventilating Systems--See note above.

Sampling System Valves The sampling system valves (43-13, 14, 28A, 28B, 29A, and 29B), which perform a containment isolation function and are tested, in accordance with the criteria in Appendix J, are identified as Clas's A valves and included in Attachment 3 of the pump and valve program.

0 r

Torus Drain Valves The torus drain valves (75-57, 58) that perform a containment isolation function are included in the program.

Drywell PSC and PSC-Reactor Building Vacuum Breakers--See note above.

SRV Discharge Line Vacuum Breakers--See note above.

Primary Containment H2 and 02 Analyzer Valves--See note above.

EECW Valves for units 1 and 2 Diesel Generator Engine Coolers--These valves are tested per Section XI requirements but were inadvertently left out of the program submittal. They are included in the updated program.

Diesel Generator Air Start Valves--See note above.

All Relief Valves Important to Safety--We have reviewed the various safety systems and have included those relief valves determined to be needed in our program.

Keep Fill Valves in Core Spray and RHR Systems These valves have been included in the progr am as indicated in the valve listing with the conditions noted in Request for Relief PV-12.

3. NRC REQUEST You requested relief for all pumps from the requirements of paragraph IWP-3220 that all pump test data be analyzed within 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> after completion of the test. We agree that a delay of an additional day before pump test data is completely analyzed is not significant if there is no delay in performing preliminary reviews of test data (including vibration levels) immediately after the test, and any pumps whose measured test parameters fall within the Code "Required Action Range" are immediately declared inoperable upon completion of the preliminary reviews. Confirm that this is your intent.

TVA RESPONSE A preliminary analysis is performed on pump test data (including vibration) immediately after the test. Any pump whose measured test parameters fall within the Code "Required Action Range" are immediately declared inoperable.

We still need four working days for performing a complete analysis of pump data per relief request PV-4.

C n

NRC REQUEST You requested relief from paragraph IWV-3411 for valves63-525 and 63-526 and propose to exercise these valves during refueling to verify that they will close. You must also verify that these valves will perform their safety-related function by passing design flow from the SLCS to the core.

Please verify that this function will also be tested during refueling.

TVA RESPONSE We verify that valves63-525 and -526 will perform their safety-related function by passing design flow from the SLCS to the core during refueling.

5. NRC REQUEST You requested relief from paragraph IWV-3411 for valves74-661 and -662 and propose to exercise these valves at each refueling because such a test entails entry into containment. We approve this request with the condition that these valves also are tested during a cold shutdown whenever the containment is de-inerted. Please pr ovide a commitment to perform tests during cold shutdown whenever possible (not to exceed thr ee months frequency) or provide justification for not commiting to this schedule.

TVA RESPONSE We do not believe the benefits of testing of valves74-661 and -662 during cold shutdown warrant the increased risks to personnel safety. These risks include working and carrying test equipment in high radiation, high temperature, and poorly accessible areas. These risks were discussed in-detail with NRC at the May 1982 meetings at Browns Ferry.

6. NRC REQUEST From a review of your IST program, the staff finds that you have elected to leak test pressure-isolation valves to verify integrity. It is the staff's position that,,when leak-rate testing is used to ve'rify the integrity of pressure isolation valves, the leakage limits selected must assure that valve sealing function has not excessively degraded. The staff does not consider relief valve capacity in setting pressure isolation valve 'leakage limits. The staff recommends a leakage limit for

'pressure isolation valves of 0.5 gpm per nominal inch of valve size with a maximum leakage rate of 5 gpm. State whether you comply with this postion. If you do not comply state and justify your acceptance test limits.

TVA RESPONSE We do not'comply with the staff recommended limits. Our Section XI acceptance test limits for Pressure Isolation Valves (PIV) are based on system relief valve capacities, which are higher than the NRC staff recommended leakage limits. However, these valves are also tested in accordance with Appendix J and with reference leakage rate acceptance criteria that are more stringent than the recommended limits. Rather than a basis of unnecessarily limiting values our acceptance criteria were chosen considering the design funct'ion of these valves and their integrated system responses with the closed loop safety systems. In practice we easily meet the recommended limits while on the other hand we do not limit ourselves to PIV leakage rates that would be less than those needed to protect the system integrity.

7. NRC REQUEST Your IST program did not indicate performance of position indicator verifications as required by the Code. Please verify that you meet this Code requirement or )ustify your failure to do so.

TVA RESPONSE We do meet the Code requirement of position indication verifications. This request was made previously in a letter from D. B. Vassallo to H. G.. Parris dated January 17, 1983, and responded to in letter from L. M. Mills to H. R. Denton dated April 6, 1983.

N

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