ML20212F849
| ML20212F849 | |
| Person / Time | |
|---|---|
| Site: | Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png |
| Issue date: | 03/02/1987 |
| From: | Frank Akstulewicz Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8703050182 | |
| Download: ML20212F849 (35) | |
Text
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'o, UNITED STATES l' > 'hE NUCLEAR REGULATORY COMMISSION
- WASHINGTON, D. C. 20$55 g /
March 2, 1987
%, . . . . f Docket No.: 50-213
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Licensee: Connecticut Yankee Atomic Power Company Facility: Haddam Neck Plant
Subject:
MEETING
SUMMARY
CONCERNING THE t!CENSEE'S PROPOSED PLANT MODIFICATIONS FOR THE RESOLUTION OF RECENTLY IDENTIFIED SMALL BREAK LOSS-0F-COOLANT ACCIDENT CONCERNS On February 18, 1987, the staff met with Connecticut Yankee Atomic Power Company (CYAPC0) to discuss the licensee's long term resolution to certain small break loss-of-coolant accidents (LOCA) and the schedule for completion '
of the subject plant modifications. By letter dated September 30, 1986. CYAFC0 has requested a one-cycle extension of an exemption from General Design Criterion 35 granted in April 1986. CYAPCO has stated that the extension is >
necessary because some plant modifications necessary to implement the per-manent solution cannot be completed until the end of the Cycle 15 outage.
Both the plant modifications and the licensee's extension request were dis-cussed during this meeting.
During the licensee's presentations, CYAPC0 described the design criteria being used for mechanical, electrical and instrumentation modifications.
CYAPCO's proposed resolution of the small break LOCA issue includes: 1) the replacement of the manual high pressure safety injection (HPSI) pump suction valves vith motor-operated valves; 2) the installation of a crosstie line be-tween the residual heat removal (RHR) and the HPSI systems; 3) the installation of HPSI injection line throttle valves and 4) the replacement of a nanual core deluge system isolation valve with a motor-operated valve.
During the presentation, CYAPC0 described the electrical problems associated with providing a redundant safety-related power source to the new motor-operated valves before the completion of the new switchgear building. CYAPCO also described the operational testing program that will be used to verify the plant operability, as well as the operating procedures to be used once the modi-fications are completed. A copy of the licensee's presentation is attached.
The staff stated that approval of the extension request was directly linked to staff review and approval of the licensee's plant modifications. As such, the staff recommended that CYAPCO submit on the docket the proposed final plant modi-fications for review and approval. The staff also concluded that an extensive single failure analysis should be submitted along with the proposed design.
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Conn Yankee Atomic Power Co. The staff indicated that in light of the pending reorganization, the licensee should expedite their submittal to assure a continuity of review and timely resolution of.this issue.
The meeting was adjourned at 12:30 p.m.
h N.
Francis M. Akstulewicz, Project Manager Integrated Safety Assessment Project Directorate Division of PWR Licensing-B
Enclosure:
As stated cc: See next page
Mr. Edward J. Mroczka Connecticut Yankee Atomic Power Company Haddam Neck Plant cc:
Gerald Garfield, Esquire Kevin McCarthy, Director Day, Berry & Howard Radiation Control Unit
, Counselors at Law Department of Environmental '
City Place Protection Hartford, Connecticut 06103-3499 State Office Building Hartford, Connecticut 06106 Superintendent Haddam Neck Plant Richard M. Kacich, Manager RDF #1 Generation Facilities Licensing Post Office Box 127E Northeast Utilities Service Company East Hampton, Connecticut 06424 Post Office Box 270 Hartford, Connecticut 06141-0270 Wayne D. Romberg Vice President, Nuclear Operations Northeast Utilities Service Company Post Office Box 270 Hartford, Connecticut 06141-0270 Board of Selectmen Town Hall Haddam, Connecticut 06103 State of Connecticut Office of Policy and Management ATTN: Under Secretary Energy Division 80 Washington Street Hartford, Connecticut 06106 Resident Inspector Haddam Neck Nuclear Power Station c/o U.S. NRC P. O. Box 116 East Haddam Post Office East Haddam, Connecticut 06423 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, Pennsylvania 19406
/
1
CONNECTICUT YANKEE ATOMIC POWER COMPANY HADDAM NECK PLANT DOCKET #50-213 FELRUARY 18, 1987 MEETING WITH NRC STAFF t
l SMALL BREAK LOCA MEDIUM BREAK LOCA ECCS MODIFICATIONS
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PURPOSE OF MEETING o TO DISCUSS DESIGN CRITERIA FOR THE SMALL AND MEDIUM BREAX LOCA HARDWARE MODIFICATIONS o TO DISCUSS PROCUREMENT STATUS AND IM?LEMENTATION SCHEDULE o PROVIDE THE STAFF WITH INFORMATION NEEDED TO APPROVE THE EXTENSION REQUEST.
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_ _ _ , - - . _ . - - _ - - . _ _ . _ . _ _ _ . - - . _. . _ . - . . . _ - . . _ _ . _ _ . - - - _ . _ _ _ _ . _ - - . _ - . _ _ _ . _ - - - _ _ . . _ _ - . _ - _ _ - - _ - - _ _ _ _ _ _ _ _ . . _ - _ _ _ _ _ _ _ _ _ . - . _ _ _ . _ _ _ . - . _ _ . _ _ _ _ a
E MEETING AGENDA HADDAM NECK PLANT - SMALL AND MEDIUM BREAK LOCAS o INTRODUCTION DEBBIE HERSEY - LICENSING o MECHANICAL MODIFICATIONS STEVE WEYLAND -MECHANICAL ENGINEERING 0 ELECTRICAL MODIFICATIONS BILL BECXER - ELECTRICAL ENGINEERING o INSTRUMENTATION 8 VINNIE MAZZIE - INSTRUMENT & CONTROLS CONTROLS o PROCEDURES NEWT YOUNG - CY SHIFT SUPERVISOR o OPERATIONAL TESTING RICK KASUGA - CY ENGINEERING o SINGLE FAILURE EVAL &
STEVE WEYLAND -MECHANICAL ENGINEERING SEISMIC DESIGN FEATURES
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SUMMARY
GERRY VArt N00RDENNEN - LICENSING
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BACKGROUND o . MARCH 31, 1986 LETTER SUBMITTED CY PSS WHICH IDENTIFIED SMALL BREAK LOCA PROBLEM o APRIL 10, 1986 LETTER DESCRIBES INTERIM MEASURES - IDENTIFIED 2 VALVES NOT SATISFYING SINGLE FAILURE CRITER10N .
o APRIL 22, 1986 REQUEST FOR TEMPORARY EXEMPTION o APRIL 23, 1983 MEETING WITH STAFF o APRIL 28, 1986 NRC GRANTED EXEMPil0N ,
o SEPTEMBER 30, 1986 REQUEST FOR EXTENSION OF SINGLE FAILURE EXEM? TION
- .o DECEMBER 12,1986 S
. PROMPT REPORT.- IDENTIFIES
- 4 8 MEDIUM BREAK LOCA PROBLEM -
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o DECEMBER 15, 1983 MEETING WITH STAFF ,
o DECEMBER 17, 1986 SUBMITTED EMERGENCY LICENSE AMENDMENT REQUEST o DECEMBER 19, 1986 SUBMITTED RESPONSES TO NRC QUESTIONS o DECEMBER 20, 1986 FLOW TEST PERFORMED, FCV-7'J6 REPOSITIONED AND LOCKED o DECEMBER 22, 1986 RECElVED WAIVER FROM TECH.
SPEC. 3.6.B o DECEMBER 24, 1983 RECEIVED EMERGENCY AMENDMENT l
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0 REPLACE MANUAL.HPSI PUMP SUCTION VALVES WITH MOVs PURPOSE: PREVENT CONTAMINATED WATER FROM ENTERING RWST, a
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o INSTALL RHR/HPSI CROSSTIE (8" PIPING) AND - ASSOCI ATED VALVES BETWEEN RHR PUMP DISCHARGE AND HPSI PUMP SUCTION PURPOSE: PROVIDE FLOW PATH FROM RHR. PUMP TO HPSI PUMP x FOR,HIGH PRESSURE SUMP RECIRC.
o INSTALL HPSI INJECTION LINE THROTTLE VALVES (TOTAL 0F 4 FOUR GLOBE VALVES, ONE FOR EACH INJECTION LINE)
\ PURPOSE: BALANCE FLOW IN EACH INJECTION LINE TO ENHANCE T
HPSI FLOW CAPABILITIES.
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,PURPOSk: 7ROVIDE REDUNDANT ISOLATION FOR C.D. HEADER, THEREBY PREVENTING LOSS OF ECCS INVENTORY DURING SHORT-TERM RECIRC. IF C.D. LINE IS BROKEN.
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HADDAM NECK PHASES OF EMERGENCY CORE COOLING
- 1. INJECTION PHASE PURPOSE: TO PROVIDE WATER FROM THE RWST IN SUFFICIENT QUANTITIES AND PRESSURES TO REC 0VER AND COOL THE CORE THE INJECTION PHASE WILL BE TERMINATED WHEN APPROXIMATELY 100,000 GALLONS HAVE BEEN PUMPED FROM THE RWST 11 SHORT-TERM SUMP RECIRCULATION PHASE .
PURPOSE: TO CONTINUE TO PROVIDE SUFFICIENT WATER TO COOL THE CORE USING THE CONTAINMENT SUMP AS A WATER SOURCE.
WATER WILL BE DELIVERED BY USING AN RHR PUMP, RHR HEAT EXCHANGER AND HPSI PUMP IN SERIES THE SHORT-TERM RECIRCULATION PHASE WILL BE TERMINATED AT 8 l HOURS AFTER THE INITIATION OF THE LOCA OR WHEN RCS PRESSURE FALLS TO BELOW 100 PSIG, WHICHEVER OCCURS LATER 111. LONG-TERM SUMP RECIRCULATION PHASE PURPOSE: 'IO PROVIDE SUFFICIENT WATER TO BOTH THE HOT AND COLD SIDES FOR CORE COOLING PLUS PROVIDE EN0 UGH EXCESS WATER TO THE NON-BROKEN SIDE TO FLUSH EXCESS BORON OUT OF k #
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-g-ECCS MODIFICATIONS DESIGN OBJECTIVES INJECTION PHASE O PROVIDE A SYSTEM WHICH WILL AUTO-START UPON RECEIPT OF A SlAS; TAKE SUCTION FROM THE RWST; DELIVER THE COOL WATER TO THE RCS AT SUFFICIENTLY HIGH PRESSURE, AND FLOW TO COOL THE CORE. ,
O THE SYSTEM SHALL BE ABLE TO TOLERATE A SINGLE ACTIVE FAILURE WITHOUT LOSS OF FUNCTIONAL CAPABILITIES.
O THE SYSTEM SHALL DELIVER ADEQUATE WATER AT SUFFICIENT PRESSURE TO COOL THE CORE FOLLOWING A LOCA 0F ANY SIZE AND LOCATION.
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ECCS MODIFICATIONS DESIGN OBJECTIVES SHORT-TERM RECIRCULATION PHASE o PROVIDE A SYSTEM WHICH CAN TAKE SUCTION FROM THE CONTAINMENT SUMP, COOL THE SUMP WATER AND DELIVER THE COOL WATER TO THE RCS AT SUFFICIENTLY HIGH PRESSURE AND FLOW TO MAINTAIN CORE COOLING o THE SYSTEM SHALL BE ABLE TO TOLERATE A SINGLE ACTIVE FAILURE WITHOUT LOSS OF FUNCTIONAL CAPABILITIES o THE SYSTEM SHALL PREVENT ENTRY OF POTENTIALLY HIGHLY CONTAMINATED SUMP WATER INTO THE RWST ASSUMING A SINGLE ACTIVE FAILURE
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9 o THE SYSTEM SHALL DELIVER ADEQUATE WATER TO COOL THE CORE FOLLOWING A LOCA 0F ANY SIZE OR LOCATION o WITH ALL OTHER INJECTION PATHS ISOLATED, THE SYSTEM SHALL BE ABLE TO DELIVER WATER TO THE RCS DOWN TO AN RCS PRESSURE OF 0 (ZER0) PSIG o WHEN THIS MODIFICATION IS FULLY IMPLEtiENTED, SUMP SWITCHOVER SHALL BE ACCOMPLISHED ASSUMING A SINGLE l ACTIVE FAILURE o ALL PIPING WHICH COULD CONTAIN RADI0 ACTIVE FLulD OUTSIDE CONTAINMENT SHALL BE CONFINED TO THE PAB OR PIPE TRENCH 1
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O ECCS MODIFICATIONS DESIGN OBJECTIVES LONG-TERM RECIRCULATION PHASE o PROVIDE A SYSTEM WHICH CAN TAXE SUCTION FROM THE CONTAINMENT SUMP, COOL THE SUMP WATER AND DELIVER SUFFICIENT WATER TO COOL THE CORE FOLLOWING A LOCA 0F ANY SIZE AND LOCATION o THE SYSTEM SHALL BE ABLE TO TOLERATE A SINGLE ACTIVE FAILURE WITHOUT LOSS OF FUNCTIONAL CAPABILITIES o THE SYSTEM SHALL PREVENT ENTRY OF POTENT.lALLY HIGHLY CONTAMINATED SUMP WATER INTO THE RWST ASSUMING A SINGLE ACTIVE FAILURE o SWITCHOVER TO LONG-TERM SUMP REClRCULATION SHALL BE ABLE TO BE ACCOMPLISHED ASSUMING A SINGLE ACTIVE FAILURE o ALL PIPING WHICH COULD CONTAIN RADI0 ACTIVE FLUID OUTSIDE
' CONTAINMENT SHALL BE CONFINED TO THE PAB OR PIPE TRENCH o THE SYSTEM SHALL BE CAPABLE, IN THE LONG TERM, OF FLUSHING EXCESS BORIC ACID FROM THE CORE REGION TO PRECLUDE BORON PRECIPITATION
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ELECTRICAL MODIFICATIONS SMALL BREAK LOCA o VALVES WILL BE POWERED DURING THE 1989 OUTAGE o "A TRAIN" LOCA LOADS WILL BE POWERED FROM A NEW MCC LOCATED IN THE EXISTING SWTICHGEAR ROOM o "B TRAIN" LOCA LOADS WILL BE POWERED FROM A NEW MCC LOCATED IN THE NEW SWITCHGEAR ROOM MEDIUM BREAX LCCA o NEW VALVE MUST BE POWERED FROM MCC5 o DISCONNECT VALVE PRESENTLY ON MCCS TO ACCOMMODATE NEW ~
VALVE (N0 SPA 3E COMPARTMENTS AVAILABLE) IN ACCORDANCE WITH DESIGN BASIS ACCIDENT REVIEW, 0
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INSTRUMENTATION & CONTROLS SMALL BREAK LOCA o VALVES WILL HAVE LOCAL MANUAL CONTROL IN 1987 o OPERATOR CONTROL FROM CONTROL ROOM WILL BE ESTABLISHED IN 1989 MEDIUM BREAK LOCA o VALVE WILL BE OPERABLE FROM SWITCHGEAR ROOM IN 1987 i
o CONTROL WILL BE TRANSFERRED TO THE CONTROL ROOM IN 1989 b
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0 STOP HPSI PUMPS O CLOSE HPSl SUCTION VALVES (SI-MOV-854A AND B)
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0 OPEN SUMP ISOLATION VALVE (RH-MOV-22 OR RH-V-808A) 0 STOP LPSI PUMPS 0 CLOSECOREDELUGEISOLATIONVALVES(SI-MOV-8flA&B-USE SI-MOV-873 AS BACKUP IF NECESSARY) 0 START ONE RHR PUMP O OPEN BOTH RHR/HPSI CROSSTIE VALVES (SI-MOV-901 AND 902)
ASSOCIATED WITH SELECTED HPSI PUMP O START SELECTED HPSI PUMP 0 OPEN ONE PORV AND ITS BLOCK-VALVE
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0 STOP HPSI PUMPS 0 CLOSE PORV AND ITS BLOCK-VALVE O CHECK TO MAKE SURE THAT SI-MOV-873 IS OPEN 0 OPEN ONE CORE DELUGE ISOLATION VALVE (SI-MOV-871 A OR B)
AND OBSERVE RHR PUMP FLOW GREATER THAN APPROXIMATELY 200 GPM 0 IF FLOW IS LESS THAN 200 GPM - REALIGN HPSI & CLOSE CORE DELUGE ISOLATION VALVE O OPEN CHARGING PUMP SUCTION VALVE (RH-MOV-33 A OR B) 0 CLOSE BA-MOV-373 (RWST TO CHARGING PUMP SUCTION VALVE) 0 OPEN CHARGING DISCHARGE ISOLATION VALVE (CH-MOV-292 B OR C)
O START ClARGING PUMP 0 THROTTLE {CHgRG NGjFL W (CH-fCV-1,10,)110A}, UN,TILgCHARG NG FLOW IS GREATE THAN200'GPMBUTTOTA3RHRPUMPFLOW DOES NOT EXCEED 2200 GPM
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INJECTION LINE BALANCING OBJECTIVE: IO SET THE THROTTLE POSITION OF EACH INJECTION l GLOBE VALVE AND PERFORM 4 LOOP INJECTION TEST.
SYSTEM llNEUP:
0 NEW CROSSTIE MOVS ISOLATED 0 HPSI MINIRECIRC. ISOLATED 0 HPSI SuCTI0tt MOVS & RWST MOV OPEN 0 (2) HPSI INJECTION LINES ISOLATED (PREFERABLY 2 & 3) 0 (2) HPSI INJECTION LINES OPEN & PRETHROTTLED TO AN APPROXIMATE POSITION TO BE DETERMINED.
0 ONE HPSI PUMP RUNNING 0 IO RECIRC. INJECTED WATER BACK TO THE RWST, RHR WILL BE LINED UP TO TAKE SUCTION FROM LOOP 1 HL AND DISCHARGE THROUGli THE Sl-MOV-0874. THIS WILL ALLOW LONGER INJECTION TIME.
O ULTRASONIC FLOW MEASURING EQUIPMENT WILL BE LOCATED ON k #) SET,
\ h 0 AFTER THE GLOBE VALVES HAVE BEEN A FOUR LOOP INJECTION TEST WILL BE PERFORMED WITH THE SAME SYSTEM LINE-UP AS ABOVE.
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RH-FCV-796 SETTING AND VERIFICATION
(~ h OBJECTIVE: TO THROTTLE RH-FCV-795 TO THE POINT BETWEE 1700
- 2000 GPM WHERE THE SUCTION PR THAT OF RHR SYSTEM LINE-UP!
O CORE DELUGE ISOLATED 0 HPSI MINIREclRC. ISOLATED 0 RHR TO CHARGING CROSSTIE ISOLATED O RHR TO LOOP 2 CL ISOLATED 0 ANY 2 HPSI INJECTION MOVS ISOLATED 0 NEW HPSI SUCTION MOVS ISOLATED 0 NEW RHR TO HPSI CROSSTIE MOVS OPEN 0 ONE RHR AND ONE HPSI PUMP WILL BE USED CORRESPONDING TO THE A & B EMERGENCY DIESEL TRAINS 0 FLOW #1LL BE MEASURED ON THE NEW CROSSTIE LINE WITH ULTRASONICS J & l$$ 4 1 'l 4 4 ( If$ j ( ! "p
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AT THIS TlHE. THEY WILL BE INSTALLED AND FLOWRATE REVERIFIED. IHE COLLARS WILL BE IN PLACE FOR THE REMAINING FLOW TESTS.
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SHORT-TERM RECIRC. FLOWTEST OBJECTIVE: TO PROVE THAT TWO LOOP INJECTION CAN PROVIDE ADEQUATE CORE COOLING FLOW AND NOT CAUSE HPSI PUMPS CAVITATION.
SYSTEM llNE-UP!
O HPSI SUCTION FROM RWST ISOLATED 0 HPSI MINIREclRC. ISOLATED 0 RHR TO LOOP 2 CL ISOLATED 0 CORE DELUGE ISOLATED O RHR TO CHARGING CROSSTIE ISOLATED 0 RHR SUCTION FROM LOOP 1 HL OPEN O HPSI INJECTION MOVS TO ANY TWO LOOPS ISOLATED 0 RHR TO HPSI CROSSTIE MOVS OPEN 0 (1) ECCS TRAIN (1 HPSI, 1 RHR) RUNNING O ULTRASONIC FLOW MEASUREMENTS WILL BE TAKEN AT LOOP INJECT!0N f LOCATI,0NS, 10 (ERIFY 4 REQUIREDy 5 ( (
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LONG-TERM RECIRC FLOWTEST OBJECTIVE: TO SHOW SUFFICIENT WATER CAN BE DELIVERED TO THE CORE FOLLOWING A LOCA 0F ANY SIZE AND LOCATION SYSTEM llNE-UP!
O RHR TO HPSI CROSSTIE ISOLATED 0 RHR TO LOOP 2 CL ISOLATED 0 (1) CORE DELUGE MOV ISOLATED (871A OR 8) 0 RHR TO CHARGING CROSSTIE THROUGH FCV-Il0 OPEN 0 (1) RHR AND (1) CHARGING PUMP DN 0 RHR SuCT10N FROM LOOP 1 HL OPEN 0 SET CHARGING FLOW AT APPROXIMATELY 200 GPM 0 RECORD FLOW THROUGH CORE DELUGE LINE BY READING FT-602.
NEW COLLARS MADE FOR FCV-795 MUST BE IN PLACE FOR THIS PHASE O TOTAL FLOW OUTPUT OF RHR PUMP SHOULD BE 2200 GPM, OR RT-602 SHOULD READ APPROXIMATELY 1700-2000 GPM.
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STRESS ANALYSIS 0 A DEADWElGHT, THERMAL AND DYNAMIC SEISMIC P!* LNG ANALYSIS WILL BE PERFORMED.
O P! PING ANALYSIS WILL BE CONSISTENT WITH THAT USED FOR SEP TOPIC lll-6 HADDAM NECK PLANT.
O THE ANALYSIS IS BASED ON THE PROVISIONS OF ANSI B31.1 POWER PIPING CODE, 1973 EDITION, SUMMER 1973 ADDENDA.
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O IHE LOADING COMBINATIONS AND ASSOCIATED STRESS LIMITS WILL BE THE SAME AS THOSE PREVIOUSLY SUBMITTED TO THE NRC FOR USE IN THE SEP topic lil-6 EFFORT.
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SCllEDULE FEBRUARY 18, 1987 -
MEETING WITH STAFF MARCH 24, 1987 -
SUBMIT STRESS ANALYSIS, STATUS OF ISl PROGRAM AND RESULTS OF ECCS REVIEW TO NRC APRIL 1, 1987 -
SuBHli LICENSE AMENDMENT REQUESTS TO NRC o JULY, 1987 -
CY OUTAGE BEGINS DURING OUTAGE -
PERFORM ISl ON CORE DELUGE PIPING COMPLETE MODIFICATIONS PERFORM FLOW IESTING PRIOR TO START-UP -
NRC APPROYAL OF NULAP CODE USED TO PERFORM LOCA ANALYSIS NRC APPROVAL OF LICENSE AMENDHENTS IMPLEMENT
, PROCEDURAL CHANGES ,
t i l$$kh,d't/&4't\4 9/)1 l '. diji OCTOBER, 1987 END OF CY OUTAGE.
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SUMMARY
o ALL PIPING MODIFICATIONS FOR B0Tli TfiE SMALL AND MEDIUM BREAX LOCA WILL BE COMPLETED DURING TliE 1987 REFUELING OUTAGE.
o ADE0VATE COOLING WILL BE PROVIDED F03 Tile INJECTION AND i
RECIRCULATION PilASES FOLLOWING A LOCA 0F ANY SIZE AND LOCATION.
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o TiiE ECCS SYSTEM WILL TOLERATE A SINGLE ACTIVE VALVE FAILURE IN 1987.
o ALL PIPING WillCil COULD CONTAIN RADI0 ACTIVE FLUID OUTSIDE CONTAINMENT WILL BE CONFINED TO TiiE PAB OR PIPE '
TRENCil, o VALVES,,WILL llAVE LOCAL MANUAL CONTROL OR BE OPERABLE FROM Tile SWITCllGEAR ROOM IN 1987.
o VALV$5 LL BE O ER b A CONT OL DRikTiiE NTkOL ROOM IN 1989 WITil Tile ADDITION OF A NEW SAFETY-GRADE-MOTOR CONTROL CENTER.
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o PROCEDURAL ACTIONS HAVE BEEN DETERMINED, o THE ECCS MODIFICATIONS WILL BE THOROUGHLY TESTED, VALVE Rl!-FCV-796 WILL BE RESET AND LOCKED TO THE PROPER POSITION, o THE SAFETY GRADE PIPING MODIFICATIONS WILL BE ENVIRON-MENTALLY AND SEISMICALLY OUAllFIED, o A REVERIFICATION OF THE ECCS SYSTEM IS CURRENTLY UNDER-WAY, NO ADDITIONAL PROBLEMS HAVE BEEN IDENTIFIED, o THE PIPING MODIFICATIONS WILL PROVIDE AN ALTERNATE MEANS OF CORE COOLING, f )
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m March 2, 1987 Conn. Yrnkee Atomic Power Co. The staff indicated that in light of the pending reorganization, the licensee should expedite their submittal to assure a continuity of revit:u and timely resolution of this issue.
The meeting was adjourned at 12:30 p.m.
(originalsignedby) francis M. Akstulewicz, Project Marager Integrated Safety Assessment Project Directorate Division of PWR Licensing-B
Enclosure:
DISTRlhcI1ON As stated centrarTTTes C7Liang
!$APD file RJones cc: See next page a rtR PDA a IAhmed i.^ocal PDP ^ CMiller J.Partiew C .Grine.,
f.AkstulcWicz PAnderson '
OCLD C .1t.t da n B.Gewet.
ACPtl,10) 2 15APDhd FAkstuicwict:cm vt . sen Oc!SAPD (C9f1mos 2/f/87 2csJ/87 3/g)87