ML20248E035
| ML20248E035 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 08/02/1989 |
| From: | Daniels T Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8908110213 | |
| Download: ML20248E035 (60) | |
Text
ga aerg g l tg UNITED STATES )
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NUCLEAR REGULATORY COMMISSION Th j , ,
.dASHINGTON. D. C. 20555
's August 2, 1939 Docket Nos. 50-259, 50-260 and S0-296
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LICENSEE: Tennessee Valley Authority FACILITY: Browns Ferry Nuclear Plant, Units 1, 2 and 3
SUBJECT:
MINUTES OF MEETINGS HELD ON JULY 10,11 AND 12,1989 WITH TENNESSEE val. LEY AUTHORITY (TVA) ON ELECTRICAL ISSUES )
1 On July 10, 11 and 12, 1989, meetings were held at Browns Ferry Nuclear Plant (BFN) between the NRC staff and the Tennessee Valley Authority. The i meetings were requested by the NRC staff to discuss electrical issues at BFN.
The following is a summary of the significant items discussed and the actions taken or proposed.
The first issue discussed on the afternoon of July 10, 1989 was cable ampacity.
The TVA proposed agenda for the meeting is Page 1 of Enclosure 1. The NRC staff's questions are on Page 2 of Enclosure 1. Page 3 cf Enclosure 1 lists those in attendance. The subsequent pages of Enclosure 1 are copies of the program overview viewgraphs used in the TVA presentation.
As a result of the discussions, the staff received a clearer understanding of TVA's table ampacity program and believes that when TVA formally documents its response to the staff questions, a final safety evaluation report can be issued on this program.
On July 11, 1989 in the morning a presentation and discussion was held concern-ing the AC/DC electric distribution necessary to support the full power opera-tion of BFN, Unit 2. Page 1 of Enclosure 2 is the agenda for the discussions and Page 2 of Enclosure 2 lists those in attendance. The subsequent pages of Enclosure 2 contain the TVA outline used during their presentation. The presentation was very good and improved the NRC staff's knowledge of the specific interlocks and interconnections between the three BFN units AC/DC electrical distribution systems.
In addition, the staff requested a briefing on the status of the Environmental Qualification Program at Browns Ferry. TVA's presentation centered around their qualification efforts on three motor control centers (MCC). Enclosure 3 contains the list of attendees and the licensee's presentation slides. TVA discussed various alternative methods for qualifications these MCCs. Presently, TVA is preparing for NRC review and approval of a variety of actions, including hardware modifications, operator actions and a possible licensee amendment to resolve '.his issue. Further discussions may be required as part of the staff's review of the licensee's proposed submittal.
Finally, on July 12, the staff and TVA discussed the recently submitted cable separation analysis dated June 6, 1989. The list of attendees is provided as 8908110213 890802 rx PLR ADOCK 05000259 PDC '
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l, Enclosure 4. 'As a result of these preliminary discussions, the following L action items were agreed on:
- 1. A follow-up, working-level meeting would be scheduled to discuss in future details the licensee's submittal. The date of this meeting would be followed by the NRC Project Manager and the TVA Manager of l
Licensing.
- 2. TVA was asked to assess the adequacy of their evaluation of all external hazards for V and V,, cables and provide the staff with a supplement to their Jude 6,1989 submittal, where appropriate. This position has been previously stated by the staff in its May 11, 1989 meeting (meeting summary dated May 26,1989).
- 3. Finally, the staff indicated that further discussions would be needed concerning the lack of inclusion of division V3 cables from the design drawing sampling effort.
E du Tom Daniels, Project Manager TVA Projects Division Office of Nuclear Reactor Regulation
Enclosures:
- 1. Ampacity Meeting Agenda and Attendance List for the July 10, 1989 Meeting
- 2. Electrical Power System Agenda and Attendance List for the July 11, 1989 Meeting
- 3. Attendance List and Handout for July 11, 1989 Meeting
- 4. Attendance List for July 12, 1989 Meeting on Cable Separation Issues cc w/ enclosures:
See next page TFC :N!fR:TVA/LA :NRR M :NRR:TNA/ :N :TVA/AD/f g,
. . ____:. {A/BC :TVA:AD/TP
..____:_____... ...___../ _:._______... i NAME :MSimms :T niels:as :AMari os : bard :RPierson . :SB1, ,
</: I DATE:7/M/89 :7/11/89 8///89 :'9// /89 : F,/1/89 4/ 89 :
' 0FFICIAL RECORD COPY
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, Meiting Summary, Mehioranda for Trip Reports or Site Visits **
Docket: Filer NRC PDR ;
l Local PDR Projects '4aading ADSP Reading J. Sniezek
. D. Crutchfield j T.QLy B. D. Liaw
.S. Black- '
i R. Pierson T..Daniels !
G. Gears !
i D. Moran N. Markisohn i M. Sinns !
.B. Wilson, Region II 1 W. S. Little OGC F. Paulitz l A. Marinos i H. Gar ACRS 10 (g )
GPA/CA (M. Callahan) (3)
E. Jordan l B. Grimes i P. Gwynn j J. Scarborough G. Marcus ,
L. Norrholm C. Ader J. Gray z R. Borchardt BFN Rdg. File
- cc: Licensee / Applicant & Service List l
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General Counsel Chairman, Limestone County Commission Tennessee Valley Authority P. O. Box 188 400 West Summit Hill Drive Athens Alabama 35611 ET 11B 33H Knoxville, Tennessee 37902 Claude Earl Fox, M.D.
State Health Officer Mr. F.-L. Moreadith . State Department' of Public Health
'Vice President, Nuclear Engineering State Office Building Tennessee Valley Authority Montgomery, Alabama 36130 400 West Summit Hill Drive WT 12A 12A Regional Administrator, Region II Knoxville, Tennessee 37902 U.S. Nuclear Regulatory Commission 101 Marietta Street, N.W.
" Dr. Mark O. Medford Atlanta', Georgia 30323 Vice President and Nuclear
. Technical Director Mr. Danny Carpenter Tennessee Valley Authority Senior Resident Inspector 6N 38A Lookout Place Browns Ferry Nuclear. Plant Chattanooga, Tennessee 37402-2801 U.S. Nuclear Regulatory Commission Route 12 Box 637 Manager, Nuclear Licensing Athenc, Alabama 35611 and Regulatory Affairs Tennessee Valley Authority Dr. Henry Myers, Science Advisor SN 1578-Lookout Place Consiittee on Interior
-Chattanooga, Tennessee 37402-2801 and-Insular Affairs U.S. House of Representatives Mr. O. J. Zeringue Washington, D.C. 20515 Site Director
~ Browns Ferry Nuclear Plant Tennessee Valley Authority Tennessee Valley Authority Rockvilla Office P. O. Box 2000 11921 Rockville Pike Decatur, Alabama 35602 Suite 402 Rockville. Maryland 20852 Mr. P. Carier Site Licensing Manager Mr. Oliver D. Kingsley, Jr.
Browns Ferry Nuclear Plant Senior Vice Fresident, Nuclear Power Tennessee Valley Authority Tennessee Valley Authority P. O. Box 2000 6N 38A Lookout Place Decatur, Alabama 35602 1101 Market Street Chattanooga, Tennessee 37402-2801 Mr. G. Campbell Plant Manager Browns Ferry Nuclear Planit Tennessee Valley Authority l P. O. Box 2000 i Decatur, Al w ma 35602 i
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4 ENCLOSURE 1 1
AMPACITY MEETING AGENDA JULY 10, 1989 .,
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CALCULATION SCOPE AND RESULTS RANDOM FILL ANALYSIS SINCE FEB 3RD MEETING It -
REVIEW OF TVA LAB TEST SET UP AND RESULTS CONCLUSIONS AND DISCUSSION G
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' ENCLOSURE 1
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L QUESTIONS' L
!- 1.- Discussion of cable tray _ test.
!' 2. Define and discuss random distribution issue.
- 3. ' Discuss difference between test and analysis.
- 4. Scope of ampacity analysis:
100% tray for V4 and V 5 100% conduit 100% sampifog for V3 '
and results.
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E_NCLOSURE 1 ATTENDANCE LIST JULY 10, 1989 MEETING :
1 Name Org6nization ;
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Masoud Bajestani TVA Jeff Hays TVA Jeff Rinne TVA i
Brian Reagan TVA John Rommel Bechtel ;
Kent Brown TVA l David Skridulis TVA Fred Paulitz NRC/NRR/TVA Angelo Marinos NRC/NRR/TVA Hukam Garg NRC/NRR/TVA Tom Daniels NRC/NRR/TVA )
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ENCLOSURE 2
' ' -JULY 11, 1989 MEETING AGENDA AC Power Systela
! * '4160V-480V 12Cf DC Power System 250V DC 125V DC Diesel Generator
- D-G for Normal Operation D-G for Appendix R Event D-G for Station Blackout Ratings .
NRC Questions 4
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- ' . 1 ENCLOSURE 2 - '. < < 7 I ; . ' ", , t '/.. i ATTENDANCE LIST , i-
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JUL? 11, 1989 MEETING . ' . ,
.'l .
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Name
. Organization
- t. ,
3 . ' *'
, . .9.. .
0*.
David'Skridulis -
- . . TVA . .'l, .
- : - ' , . '
_ Jerry Nicely TVA . ,' . . - *; ;~ 5 %. . l. ., ,
Jeff Hays .
, . TV A . .
Angelo Marinos .
, NRC/NRR/TVA *
. Hukam Garg '
. NRC/NRR/TVA ' * ' '
Tom Daniels -
NRC/NRR/TVA . .
Fred Paulitz '-
NRC/NRR/TVA.' '
l
+
Jeff Rinne TVA . .. .
Pranab Goha . . TVA '
Malcolm Pyatt TVA . .
Bill Nelson
. TVA ,. .
Steven A. Hilmes TVA , .
Masoud Ba,jestani
, TVA ,
Edwin Freeman ,
TVA 6
5 9
em i
.2-m_____.___ _ _ _ _ __ _ _ _ _ _ _ _ . . _ _ . _ _ _ _ _ _ . _ . . _ _ _ _ _ _ _ . _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ . _ . _ . _ _ . _ _ _ _ _ m _ _ _ _ __m__m.__________ _ _ _ _ _ _ _ _ _ _ _ _. _ _ _ _ . _ _ . ____m
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ENCLOSURE 2 l
~
4KV-AND 480V NORMAL AND STANDBY APS DESIGNED IN ACCORDANCE WITH IEEE 308-1971 OFFSITE POWER SUPPLIES EACH CONNECTION MEETS THE CAPACITY AND .
CAPABILITY REQUIREMENTS OF GDC-17 MAIN TRANSFORMERS FOR EACH UNIT FED FROM 500KV SWITCHYARD WHICH IS SUPPLIED BY 7 500KV LINES CSSTS ARE FED FROM 161 KV SWITCHYARD WHICH IS SUPPLIED BY TWO 161 KV LINES ONSITE STANDBY POWER SOURCES EACH 4 KV SHUTDOWN BOARD HAS A CONNECTION TO ONE OR MORE DGUs EACH DGU MEETS THE CAPACITY REQUIREMENTS OF SAFETY GUIDE 9 9
0317e/7
._____.__--__._-.--_-___-_m_ _ . _ _ . _ _ _ _ . . _ _ . _- .._ _ . _ . - - .
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- c 4KV BUS TRANSFER SCHEME, 'l l . ,. ,
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COORDINATED TRANSFER SCHEMZ l ,,
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AUTO TRANSFERS INITIATED BY:
,. GENERATOR & TRANSFORMER PROTECTIVE RELAYS l '
1 ,
DEGRADED UV ON 4KV SHUTDOWN BDS ,
LOV AT NORMAL SUPPLY BREAKER ,
ACCIDENTAL TRIP OF NORMAL SUPPLY BREAKER l .
FAST BUS TRANSFERS VOLTAGE SUPERVISED SLOW BUS TRANSFERS:
- 4KV SHUTDOWN, BUSES 9 2.4 SEC 4KV SHUTDOWN BOARDS 9 3.0 SEC 4KV UNIT BOARDS 9 3.7 AUTOMATIC RETURN TO NORMAL (SHUTDOWN BOARD ONLY) 4KV LOPES ARE NOT SEQUENCED ,
- l DEGRADED VOLTAGE
- 2 OUT OF 3 LOGIC OVERVOLTAGE SET AT 4400V
. ANNUNCIATION ONLY UNDERVOLTAGE SET AT 3920V
. DG STARTED 9 4.0 SEC
. LOAD SHED INITIATED 9 6.9 SEC 1
1 LOSS OF VOLTAGE LOGIC i
0320e/9 l I
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120V AC POWER DISTRIBUTION SYST,,E,H THREE SYSTEMS FED FROM 3AFETY-RELATED-BOARDS:
208/120V AC I & C POWER SYSTEM -
2 REDUNDANT I & C BUSES EACH UNIT NORMAL POWER SUPPLY FROM 480V SHUTDOWN BOARDS D-G BACKED .
UNIT PREFEnnen 240/120V POWER SYSTEM ONE DISTRIBUTION BUS EACH UNIT NORMAL POWER FROM MMG SET MMG SET CONSISTS OF DIRECT COUPLED:
- --480V AC MOTOR
--250V DC MOTOR
--FLYWHEEL'
--740/120V.1/ AC GENERATOR NORMALLY GEN DRIVEN BY AC MOTOR AND FLYWHEEL-ON LOSS OF AC, DC MOTOR TAKES OVER TO DRIVE 1
{
2 DISTRIBUTION BUS PER UNIT t
NORMAL POWER FROM MG SET MG SET CONSISTS OF 480V MOTOR 120V 1/ AC GENERATOR I D-GBACKED(MANUALLY) j 0320e/10
e
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250V DC POWER DISTRIBUTION SYSTEM I '
TWO SAFETY SYSTEMS
- 3-UNIT BATTERIES 5 SHUTDOWN BOARD BATTERIES
- MEETS THE INTENT OF THE INDEPENDENCE, REDUNDANCY, AND SINGLE-FAILURE CRITERIA REQUIREMENTS OF IEEE 279-1971 SYSTEM IS DESIGNED SO THAT BATTERIES CANNOT BE' PARALLELED 0320e/2 l
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250V DC POWER DISTRIBUTION SYSTEM UNIT BATTERIES i
THREE 120 CELL (LEAD-CALCIUM ACID) 1 BATTERY AND CHARGER PER UNIT 1 SPARE BATTERY CHARGER FOR ALL UNITS SUPPLIES 250V DC POWER TO:
4EV SHUTDOWN BOARDS 3EA, ,3EC, 3ED 3 250V RMOV BUSES PER UNIT (2 DIV I E 1 DIV II)
- ADS, HPCI, RCIC LOADS REDUNDANT SYSTEMS / UNIT'HAVE SEPARATE NORM AND ALT
- ONER SUPPLIES ALL MANUAL TRANSFERS (ADMINISTRATIVELY CONTROLLED)
BATTERY CAPACITY BASES: 2/3 UNIT BATTERIES CAN SUPPLY (FOR 30 MINUTES W/O CHARGERS) THE SAFETY LOADS OF 1 UNIT IN DBA AND THE OTHER TWO UNITS IN COLD SHUTDOWN 0320e/3 .
- - _ _ ----_--------_-_--_ _ ___ _____ _ _ _ _ _ J
) ly -
e 250V DC POWER DISTRIBUTION SYSTJM SHUTDOWN BOARD BATTERIES 5 - 120 CELL (LEAD-CALCIUM ACID)
I ONE BATTERY AND CHARGL2 FOR EACH OF 4KV SHUTDOWN BOARDS A, B, C, D, 3EB ONE SPARE CHARGER FOR ALL FIVE BOARDS 250V DC CONTROL BUS FOR EACH SDBD HAS
_ NORMAL FEED FROM SDB BATTERIES WITH ALTERNATE FROM UNIT BATTERIES THRU MANUAL TRANSFER SWITCH SUPPLIES BREAKER CONTROL / INSTRUMENTATION FOR 4"V SHUTDOWN BOARDS A, B, C, D, 3EB LOSS OF ONE LATTERY AFFECTS NORMAL CONTROL POWER ONLY FOR 4KV SHUTDOWN WHICH I'T SUPPLIES 0320e/4 h _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ . _ _ _ _ _ . _ _ _ . . _ - _ . _ . . _ _ _ _ a
U O
250V DC POWER DISTRIBUTION SYSTEM CHARGERS PROVIDES'250V DC SUPPLY DURING NORMAL OPERATION HAS CAPACITY TO FURNISH FLOATING EQUALIZING, AND FAST CHARGE FOR BATTERIES.
SIZED TO RECHARGE IT'S BATTERY FROM FULLY DISCHARGED CONDITION IN APPROXIMATELY 12 HOURS UNDER NORMAL LOAD CONDITIONS.
0320e/S
.-2 0
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125V DC POWER SYSTEM DEDICATED TO DIESEL GENERATOR SYSTEM SUPFLIES 125V DC LOADS FOR:
DG CONTROL POWER GOVERNOR BOOSTER PUMPS FUEL PUMPS PIELD FLASHINGS ONE 60-CELL BATTERY FOR EACH DIESEL GENERATOR EACH BATTERY HAS A NORMAL AND ALTERNATE CHARGER CHARGERS POWERED FROM 480V DIESEL AUXILIARY BOARDS s
0320e/1
_ _ _ _ _ _ _ _ _ _ __ __ .____ _ _ _ _ . __-__ __________._._...____._..__.____.____m_.-_____.___-__________.________.____._._____.___...m_
_ ___ ,___ __.a..__u-____m_______ ____.__________"__J
I.
i l
NUMBER OF DIESEL GENERATORS REOUTRED TO BE OPERABLE FOR UNIT 2 RESTART NORMAL OPERATION (TECHNICAL SPECIFICATIONS): 6 OF 8 STATION BLACKOUT (3 UNIT OPERATION): 0 OF 8 (UNIT TO BE SHUT DOWN ON DC POWER SYSTEM)
APPENDIX R: 8 OF 8 0320e/6
Numbat g[ Q1esel deneratore Reavired for_ Unit [ Restart Technical 5=scifi=ations C intecratien cf the three unrts Unit 2 Technical Specifications (TS) require all f=ur Unit 1/2 diesel generatcrs CDG) to be operable.
Unit 2 75 require all three trains of Standby Gas Treatment CSEGT) to be =perabis. "C" train of SEGT is peuered for Mkv shten, bd. 3ED. Therefore, DG 3E 1s, required to be ccerable.
Unit 2 TS require both trains of Centrol Recm Emergency ventilation CCREU) to be acerable. "B" train of CREU is powered frcm the c=ntrol bay vent bd. B which is pcwered from 4kv shton. bd. 3EC. Therefore, DG 3EC is required to be operable.
In ceder te meet Unit 3 diessi generatcr support requirements one cf the Unit 3 48Dv diesel auxiliary bds.
is required to be operable to sucp=rt cperation cf DGs 3EC, and 3ED.
- In conclusion, DGs A, B, C, D, 3EC, and 3ED are required at a minimum. If RHRSU pump C3 is required fcr EECW cperation then DG 3ES ulll also be required DGs taken credit for by the Station' Blackout Analgsis Since the current T5s require 5 emergency a= ==wer scurces to operate safe shutdown equipment Cbring the plant to het standby) for the 3 licensed units following a 1 css of offsite power, no credit was taken fcr the use of the remaining 2 diesels as alternate ac power sources.
- Therefore, there are B DGs net credited as alternate ac power sources. The station b..ackcut analysis documents that the plant will be placea in a het standy ==ndition using the staticn's dc pcuer systems.
03s taken credit for by .the Accendix R Analysis The analysis defines the safe shutdown equipment and ccwer i supplies CDGs) required te mitigate a fire in a given fire zone. The combinations of DGs identified to supply cower i to the safe shutdown equipment includes the use of all 8 DGs. This is based cn'the Appendix R analysis.
- ._ _ - _ _ _ _ _ _ - _ _ _ _ - .____________-__-________-x-
I , .
DEFINITIONS 1
1 I. ENGINE -
MAXIMUM FCdER OUTPUT (COLD): THIS 'S I THE MAXIMUM AMOUNT OF POWER THAT THE PRENARMED ENGINE CAN SUPPLY DURING THE FIRST 3 MINUTES OF OPERATION WHIIJE THE TURBO-CHARGER IS DRIVEN BY THE ENGINE GEAR TRAIN MAXIMUM POWER OUTPUT (HOT): THIS IS THE MAXIMUM AMOUNT OF POWER THAT THE ENGINE CAN SUPPLY ONCE THE TURBO-CHARGER HAS HEATED SUFFICIENTLY TO BE DRIVEN TOTALLY BY THE ENGINE EXHAUST.
LOAD CARRYING CAPABILITY: THIS.IS THE MAXIMUM AMOUNT OF POWER THAT THE ENGINE CAN CONTINUOUSLY SUPPLY WITHCUT EXCEEDING ITS THERMAL DESIGN LIMITS II. g}E RATOR -
CURRENT LIMIT: THIS IS THE MAXIMUM AMOUNT OF CURRENT THAT THE GENERATOR CAN CONTINUOUSLY SUPPLY WITHOUT EXCEEDING ITS THERMAL DESIGN LIMITS 0320e/8
}
. ~ , .
1 DIESEL ENGINE LIMITATIONS l 1. CONTINUOUS AND SHORT TIME RATINGS:
! t DERATING FACTORS MUST BE APPLIED WHEN:
ENGINE JACKET WATER DISCHARGE TEMPERATURE EXCEEDS 190*F AND THE AMBIENT AIR TEMPERATURE EXCEEDS 90*F
- 2. INSTANTANEOUS RATINGS.
DERATING FACTORS MUST BE APPLIED WHEN THE AMBIENT AIR TEMPERATURE EXCEEDS 90*F 0320e/7
L- ,
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TABLE 2t DIESEL GENERATOR RATINCS ,
I
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)
- 1. Ensina - Mar 4== steady-state active 0 - 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> Short-Tine power output 2560/2a00* N (running N)
- 2. Ensina - Mazinun steady-state active > 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> Continuous power output 2600/2550* N (runnfng N)
- 3. Engina - Maw 4- = instantaneous active 0 - 3 ninntes Instantaneous power output (Cold) .
(running N + starting N) i 2150/2215* EV
- 4. Engine - mmh == instantaneous active > 3 minutes Instantaneous power output (Hot) (runninn N + starting N) 3050/3025* N f
~
- 5. Generator - Mazianna steady-state 0 - 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> Short-Time apparent power output 1515 NA '
(rtunning DA)
- 6. Generator - Maw 4-= steady-stata > 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> Continuous apparent power output 3250 EVA (running NA)
- 7. Engine - The engine can be operated at this 2000 hours0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br /> per year rating for 2000 hout s, which will 2850/2793* Xl be equivalent to the, wear of an engine operating at the continous i
rating for one year.
- Derated for 97 degrees (T) intake air tenparature. Non-darated l value applies for 1 90 degrees (F).
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ENCLOSURE 3 ATTENDANCE LIST-JULY 11, 1989 MEETING Name' ' Organization Art Alford TVA Steven A. Hilmes TVA
< Danny A. Walker TVA .
A Pranab K. Guha TVA Ken Greene TVA Roy Martin TVA
-Pedro Salas TVA
% Dave Burrell TVA Ed Dykes- TVA Gerry Gears NRC/NR2/TVA Bob Pierson NRC/NRR/TVA G. Hubbard NRC/NRR/TVA Kant W. Brown TVA Tom Daniels NRC/NRR/TVA Charles E. Anderson TVA Henry L. Jones TVA Angelo Marinos NRC/NRR/TVA Hukam Garg _ NRC/NRR/TVA Fred Paulitz NRC/NRR/TVA Mark Jacobuj Sandia Vern Nicolette Sandia Dale Jackson TVA
. ENCLOSURE 3 e
EQ EFFORT ASSOCIATED WITH MBO-U RMOV BDs 2D & EE and 250-U RMOV BD 2C ein O
e h
1 A__m_____ _____r__ 1. . 4
J:. .. '
a OBJECTIVES I.
INFORM NRC OF MCC EQ CMRONOLOGY II. OBTAIN'NRC CONCURRENCE'ON PROPOSED CORRECTIVE ACTIONS-REQUIRED TO REMOVE SUBJECT RMOV BDs FROM EQ PROGRAM m
em
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m._ _ _ _ . _ , _ _ _ . _ _ _ _. ._______.___.___m.____.__________.___m_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ __ ._.m_ _ _..-._mo______._.___ _.m.-_. _________
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e MEC ED CHRONOLOGY
. A. . MCC QUALIFICATION EFFORT-o ANALYSIS o TESTING B. MCC-ELIMINATION FROM EQ PROGRAM i
o ENCLOSURES /HUAC o ANALYSIS TO DETERMINE OTHER CORRECTIVE ACTIONS-o PROPOSAL OF ALTERNATE METHODS I
I i
4 I
3
, _ _ , . . __ w-.a--.--- - . - ' - - - - - - - - - - - -
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ANALYSIS A. ENVIRONMENTAL FAILURE MODES ANALYSIS o MARSH ENVIRONMENT DEFINED o ENVIRONMENTAL CONDITIONS IDENTIFIED FOR RMOV BG AREAS o FAILURE TIME FRAMFS IDENTIFIED FOR EACH RMOV BD B. FUNCTIONAL REQUIREMENT / FAILURE IMPACT ANALYSIS o ADDRESS SAFETY ACTIONS PER 10CFRSO.49 EVENT a SAFETY ACTION TIME FRAMES vs RMOV BD FAILURE TIME FRAMEb o IDENTIFY CORRECTIVE ACTIONS CALTERNATE METHODS) REQUIRED TO ASSURE SAFETY ACTIONS IMPACTED BY RMOV BD FAILURE .
4 9
n 1
ALTERNATE METliggg
- 1. MBO-U RMuu BDn 2D & 2E-o REWIRE THE RMOU BD COMPARTMENTS. ASSOCIATED WITH THE LPCI INJECTION VALUES CFCU-74-53 AND FCU-74-67).
o DEENERGIZE RHR PUMP MINI-FLOW UALUES CFCU-74-07 & FCU-74-30)-PRIOR TO STARTUP. RESTORE POWER PRIOR TO SHUTDOWN COOLING.
o PROUIDE EMERGENCY BYPASS SWITCHES TO ASSURE OPERATION OF EITHER RHR TEST RETURN LINE UALUE CFCU-74-SS OR FCU-74-73) AFTER PIPE' BREAK OPC.
o DENERGIZE RMOU BDs AFTER PIPE BREAK IPC.
o LICENSING AMENDMENT - REQUIRE ONLY CORE SPRAY FOR LOW PRESSURE CORE COOLING AFTER PIPE BREAK OPC.
- 2. Eso-u'RMOU BD 2C
- o ADD AN ACCUMULATOR / CHECK UALUE ARRANGEMENT TO NON-ADS SRUs ON 250-U RMOV BDs 2A & 2B TO ASSURE MANUAL DEPRESSURI2ATION CAPABILITY.AFTER PIPE BREAK OPC.
o RELOAO RCIC OUTBOARD STEAMLINE ISOLATION UALUE CFCV-71-03) AND RCIC PUMP MINI-FLOW UALUE CFCV-71-34)
MOTIVE POWER AND RCIC OIU I CONTROL LOGIC TO ESO-U RMOV ED 28.
o DEENERGIZE RMOV BD TO PREVENT SPURIOUS OPERATION OF EQUIPMENT AFTER PIPE BREAK IPC.
5 numm-----_.-.x_--____--_ - _ - . _ . - _ . _ .
CONCLUSION
, ALTERNATE METHODS DROP MCCs FROM EQ PROGRAM
- o. SINGLE FAILURE CRITERIA' SATISFIED o CSCS OBJECTIVES SATISFIED o SAFE SHUTDOWN OBJECTIVES SATISFIED O
O e
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'RMOV BD ALTERNATE METHODS J
- 1. MBO-U RMOU BDn 2D & 2E o REWIRE THE RMOV BD COMPARTMENTS ASSOCIATED WITH THE LPCI INJECTION UALUES (FCU-74-53 AND FCU-74-57) TO PREVENT SPURIOUS OPERATION AFTER PIPE BREAK OPC.
o PREVENT FAILURE OR SPURIOUS OPERATION OF RHR PUMP MINI-FLOW UALUES (FCV-74-07 & FCU-74-30) BY DEENERGIZING UALUES IN OPEN POSITION PRIOR TO STARTUP. RESTORE POWER PRIOR TO INITIATION OF SHUTDOWN COOLING.-
o PROVIDE TWO EMERGENCY BYPASS SWITCHES TO ASSURE OPERATION OF EITHER OF TWO RHR TEST RETURN LINE ISOLATION VALUES CFCU-74-SS OR FCV-74-73) AFTER PIPE BREAK OPC. A 15 MINUTE MISSION TO EITHER MSO-U-RMOV BD 2A OR 2B (MILD, ENVIRONMENTAL CONTROLLED AREAS) IS REQUIRED TO ESTABLISH TORUS' COOLING WITHIN APPROXIMATELY-2 HOURS AFTER EVENT INITIATION.
o DENERGIZE RMOV BDs AFTER PIPE BREAK IPC. A 10 MINUTE MISSION TO MBO-U SD Bus 2A & 2B (MILD, ENVIRONMENTAL CONTROLLED AREAS)
MUST BE COMPLETE WITHIN 10 HOURS AFTER EVENT INITIATION.,
o LTCENSING AMENDMENT TO REVISE THE FSAR TO REQUIRE ONLY CORE SPRAY FOR LOW PRESSURE CORE COOLING FOLLOWING PIPE BREAK OPC.
- 2. 250-U RMOV BD 2C o RELOAD 1 OF 3 NON-ADS SRVs ON 2SO-U RMOV BD 2B TO ESO-U RMOV BD 2A. ADD AN ACCUMULATOR / CHECK UALUE ARRANGEMENT (FROM UNIT
- 1) TO THE 3 NON-ADS SRVs ON ESO-U RMOV BD 2A AND TO THE REMAINING 2 NON-ADS SRVs ON 2SO-U RMOV BD 2B TO ASSURE REMOTE MANUAL DEPRESSURIZATIGN CAPABIL.'TY AFTER PIPE BREAK OPC.
o RELOAD RCIC OUTBOARD STEcML5 ISOLATION UALUE (FCV-71-03) AND RCIC PUMP MINI-FLOW UALUE 4 FLU-71-34) MOTIVE POWER AND RCIC DIU I CONTROL LOGIC TO ESO-U RMOU BD 2B.
i c DEENER'U2E RMOV BD AFTER PIPE BREAX IPC. A 10 MINUTE MISSION TO BATTERY BD 1 IN CONTROL BUILDING (MILD, ENVIRONMENTAL CONTROLLED AREA) MUST BE COMPLETE WITHIN 17 HOURS AFTER EVENT INITIATION.
e
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--. *a <
., .,r- ~ ENCLOSURE 4 JULY 12,1989 MEETING CABLE SEPARATION ISSUES
'Name _ Organization Gerry Gears Angelo Marinos NRC/NRR/TVA NRC/NRR/TVA Fred Paulitz NRC/NRR/TVA Hukam Garg.
NRC/NRR/TVA Jeff Rinne TVA David Skridulis TVA Tom Daniels NRC/NRR/TVA Pranab K. Guha TVA
_ _ _ _ _ - _ _ . _ . - .m ...__m.m__. _. _.____.. __A____.____.-_2_-_______._-_ _ ____ _ _ . _ _