ML20031B248
| ML20031B248 | |
| Person / Time | |
|---|---|
| Site: | Maine Yankee |
| Issue date: | 09/17/1981 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20031B247 | List: |
| References | |
| TASK-2.K.1 IEB-79-06, IEB-79-6, NUDOCS 8110010091 | |
| Download: ML20031B248 (2) | |
Text
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'c UNITED STATES
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[,j NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555
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- y SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION FOR MAINE YANKEE ATOMIC POWER COMPANY, MAINE YANKEE ATOMIC POWER STATION DOCKET NO. 50-309 -
INTRODUCTION On March 28, 1979 the Three Mile Island Nuclear Power Plant, Unit 2 (TMI-2) experienced core damage which resulted from a series of events which were initiated by a loss of feedwater transient. Several aspects of the acci-dent have generic applicability at operating (enter NSSS) reactors. On April W,1979,iEf u11etin 79-06 was sent to all Combustion Engineering -
B operating plant licensees. The kurpose of the Bulletin.was to provide information concerning the accident at TMI-2 and to renuest certain actions be taken by licensees to preclude a similar occurrence at their facilities. This bulletin was superseded and' expanded by IE Bulletin 79-06B dated April 14, 1979. By letters dated April 26, May 4 and 14, July 2,ard August 10, 1979, Maine Yankee Atomic Power Company provided respo1ses in conformance with the requirements of the Bulletins.
EVALUATION In the two year period since the Bulletin (s) hav'e been implemented we have observed, in addition to our review of the responses enumerated above, that the licensee has complied with all the following provisions of the Bulletins:
- Understanding of the TMI-2 sequence of events.
- Review Plant Procedures for coping with accidents and transients.
- By review of procedures and training instructions:
(1) to avoid overriding automatic action of ESF, (2) to keep high pres'sure injection (HPI) system in operation for at least 20 minutes and to maintain 50 F subcooling margin, (3) to correlate HPI initiation with reactor coolant pump (RCP) opera-tion, and (4) to train operators not to rely on pressurizer level only, to deter-mine primary coolant inventory.
- Verification of emergency feedwater (EFW) valve positions and all safety-related valve positions to ensu e proper ope ~ ion of EFW and ESF.
O!d 9
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. f
- By review of containment isolation initiation ind design for avoidance.of isolating lines that are needed to avoid degraded core cooling capability.
- By preparing and implementing procedures for all valves which could defeat or compromise flow of EFW.
- By revie. ing operating modes and procedures to prevent inadvertent pumping of. radioactive gasses and liquids out of the primary containment.
- By 7eviewing procedures related to maintenance and tast of safety-related
. systems to:
(1) verify operability of. redundant system. prior to removal of any system
~~
from service, (2) verify operability of all systems fo11owf6g maintenance or testing, and (3) verification to ope ating personnel whenever a system is removed from or returned to service.
' ~
- By developing procedures and training operators to establish and maintain natural circulation.
- By trdrifiig"6pefit6rs' to takeinto account reactoF vessel integrity cont siderations du>ing any accident c. transient.
- By performing analyses and design modificaticas to reduce the likelihood of automatic PORV actuation during anticipated transients.
- By providing ;"ocejures and training operators for a prompt manual reactor t.-1p for transients that result in a pressure increase in the reactor coolant system.
- By providing for prompt reporting within one hour of the time the reactor is not in a controlled.or expected condition of operation.
- By proposing any needed Techni al Specificatit, changes to implement any of the above parts of the Bulletins.
CONCLUSIONS Based on our review of the information provided by the lic3nsee in response to IE Bulletins, we conclude that the licensee has acceptably responded to these Bulletins. The' actions taken by the licensee demonstrate its understanding of the concerns and implications of the TMI-2 accident as they relate to the Maine Yankee Atomic Power Station. These actions have resulted in added assurance for the continued protection of the public health and safety during plant operation.
Dated: SEP 171981
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UNITED STATES NUCLEAR REGULATORY COMMISSION g
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SEP 171981 Docket No. 50-309 Mr. Robert H. Groce Senior Engineer - Licensing Maine Yankee Atomic Power Company 1671 Worchester Road Framingham, Massachusetts 10701
Dear Mr. Groce:
We have completed a review of the infonnation you have provided in letters dated April 26, May 4 and 14, July 2 and August 10, 1979, in response to IE Bulletins 79-06 and 79-06B for the Maine Yankee Atomic Power Station. The enclosed Safety Evaluation addresses the completeness and, acceptability of the responses.
Your responses-to;;}E Bulletin 79-06C, regarding the operation of the
?
reactor coolant pumps following a loss-of-coolant accident'will be reviewed separately as part of NUREG J737 Item II.K.3.5.
The issuance of this evaluation completes Item II.K.1, IE Bulletins, for your facility.
Sincerely,
-5 Robert A. Clark, Chief Operating Reactors Branch #3 Division of Licensing s
Enclosure:
Safety Evaluation CC W/enClGT,GTs; See next page 4
9 6
I I
Maine Yankee Atomic Power Company cc:
E. W. Thurlow, President Mrs. 't. Patricia Doyle, Presid'ent Maine Yankee Atomic Power Company SAFE POWER FOR MAINE Edison Drive Post Office Box 774 Augusta, Maine 04336 Camden, Maine 04843 Mr. Donald E. Vandenburgh First Selectman of Wiscasset Vice President - Engineering Municipal Building Yankee Atomic Electric Company U. S. Route 1 20 Turnpike Road Wiscasset, Maine 04578 Westboro, Massachusetts 01581 John A. Ritsher, Esquire lupper and Bradley Ropes & Gray 102 TEwnsend Avenue 225 Franklin Street Boothbay Harbor, Maine 04538 Boston, Massachusetts 02110
^
' David Santee Miller, E3q.
Mr. Rufus E. Brown 213 Morgan Street, N. W.
Deputy Attorney General Washington, D. C.
20001 State of Maine Augurts,.g.aine 04330 Mr. Paul Swetland
-- c r-N ;f x P.esident Tnspector/ Maine Yankee ~
Mr. Nicholas Barth c/o U.S.N.R.C.
Executive Director P. O. Box E Sheepscot Valley Conservation Wis: asset, Maine 04578 Association, Inc.
P. O. Box 125 Mr. Charles B. Brinkman Alan, Maine 04535 Manager - Washington Nuclear Operations Combustion Engineering Inc.
Wiscassett Public Library Association 4853 Cordell Avenue, Suite A-1
.High Street Bethesda, Maryland 20014 Wiscasset, Maine 04578 Mr. John H. Garrity, Director Mr. Torbet H. Macdonald, Jr.
Nuclear Engineering & Licensing Office of Energy Resources Maine Yankee Atomic Power Company State House Station #53 Edison Drive Augusta, Maine 04333 Augusta, Maine 04336 Robert M. La::o, Esq., Chairman Atomic Safety and Licensing Board U.S. Environmental Protection Agency U.S. Nuclear Regulatory Commission Regior, I Office Washington, D. C.
20555 ATTN: EIS COORDINATOR JFK Federal Building Dr. Cadet H. Hand, Jr., Director Boston,Massachgsetts 02203 Bodega Marine Laboratory University of California Bodega Bay, California 94923 Mr. Gustave A. Linenberger Atomic Safety and Licensing Board State Planning Officer U.S. Nuclear Regulatory Corrmission Executive Department Washington, D. C.
20555 189 State Street Augusta, Maine 04330 A
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'o, UNITED STATES NUCLEAR REGULATORY COMMISSION g $*.r,(
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WASHINGTON, D. C. 205%
%l.....
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION FOR MAINE YANKEE ATOMIC POWER COMPANY MAINE YANKEE ATOMIC POWER STATION DOCKET NO. 50-309 -
' INTRODUCTION On March 28, 1979 the Three Mile Island Nuclear Power Plant, Unit 2 (TMI-2) experienced core damage which resulted from a series of events which were initiated by a less of feedwater transient. Several aspects of the acci-dent have generic applicability at operating (enter NSSS) reactors. On April IV,1939, IE;-Bulletin 79-06. was sent to all Combustion Engineering -
operating plant licensees. The purpose of the Bulletin was to provide information concerning the acci6 ant at TMI-2 and to request certain actions be taken by licensees to preclude a similar occurrence at their facilities. This bulletin was superseded and" expanded by IE Bulletin 79-06B dated April 14, 1979. By letters dated April 26, May 4 and 14, July 2,and August 10, 1979, Maine Yankee Atomic Power Company provided responses in conformance with the requirements of the Bulletins.
EVALUATION In the two year period since the Bulletin (s) have been implemented we have observed, in addition to our review of the responses enunerated above, that the Itcensee hits complied with all the following rrovisions of the Bulletins:
- Understanding of the TMI-2 sequence of events.
- Review Plant Procedures for coping with accidents and transients.
- By re,!ew of procedures and training instructions:
(1) to avoid overriding automatic action of ESF, (2) to keep high pressure injection (HPI) system in operation for at least.20 minutes and to maintain 50 F subcooling margin, (3) to correlate HPI initiation with reactor coolant pump (RCP) opera-tion, and (4) to train operators not to rely on pressurizer level only, to deter-(
mine primary coolant inventory.
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~
- Verification of emergency feedwater (EFW) valve positions and all safety-r related valve positions to ensure proper operation of EFW and ESF.
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1
~
- By review of containmen'- isolation initiation anii design for avoidance.of
~
isolating lines that are needed to avoid degraded core cooling capability.
- By preparing and implementing procedures for all valves which could defeat or compromise flow of EFW.
- By reviewing operating modes and procedures to prevent inadvertent pumping of, radioactive gasses and liquids out of the primary containment.
- By reviewing procedures related to maintenance and test of safety-related systems to:
(1) verify operability of redundant system prior to removal of any system
~
from service, (2) verify operability of all systems followtiig maintenance or testing, and (3) verification to operating personnel whenever a system is removed from or returned to service.
- By developing procedures and training operators to establish and maintain natural circulation.
- By trIilififf6pepit5rs' to takeinto account reacto'r' vessel integrity cont siderations during any accident or transient.
- By performing analyses and design modifications to reduce the liWihood of automatic PORY actuation during anticipated transients.
- By providing procedures and training operators for a prompt manual reactor trip for transients that result in a pressure increase in the reactor coolant system.
- By providing for prompt reporting within one hour of the time the reactor is not in a controlled.or expected condition of operation.
- By proposing any needed Technical Specification changes to implement any of the above parts of the Bulletins.
C0flCLUSI0tlS Based on our review of the information provided by the licensee in response to IE Bulletins, we conclude tt.at the licensee has acceptably responded to these Bulletins. The' actions taken by the licensee demonstrate its understanding of the concerns and implications of the TMI-2 accident as they relate to the Maine Yankee Atomic Power Station. These actions have resulted in added assurance for the continued protection of the public health and safety during plant operation.
Dated: SEP 171981 e
A PDE p* at rug je UNITED STATES j,(
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WA5mNGTON. D. C. 20555 f
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SEP 171981 Docket No. 50-309 Mr. Robert H. Groce Senior Engineer - Licensing Maine Yankee Atomic Power Company 1671 Worchester Road Franingham,11assachusetts 10701
Dear Mr. Groce:
We have completed a review of the information you have provided in letters dated April 26, May 4 and 14, July 2 and August 10, 1979, in response to IE Bulletins 79-06 and 79-06B for the Maine Yankee Atomic Power Station. The enclosed Safety Evaluation addresses the completeness and, acceptability of the responses.
Your responses-to;;}E7 Bulletin 79-06C, regarding the operation of the reactor coolant pumps following a loss-of-coolant accident will be reviewed separately as part of NUREG-0737 Item II.K.3.5.
The issuance of this evaluation completes Item II.K.1, IE Bulletins, for your facility.
Sin :erely, 7
[
Robert A. Clark, Chief Operating Reactors Branch #3 Division of Licensing
Enclosure:
Safety Evaluation cc w/ enclosure:
See next page 8
(
Maine Yankee Atomic Power Company cc:
E. W. Thurlow, President Mrs.'L. Patricia Doyle, Presid'ent Maine Yankee Atomic Power Company SAFE POWER FOR MAINE Edison Drive Post Office Box 774 Augusts, Maine 04336 Camden, Maine 04843 Mr. Donald E. Vandenburgh First Selectman of Wiscasset Vice President - Engineering Municipal Building Yankee Atomic Electric Company U. S. Route 1 20 Turnpike Road Wiscasset, Maine 04578 Westboro, Massachusetts 01581 Stanley'R. Tupper, 'Esq.'
~
John A. Ritsher, Esquire Tupper and Bradley Ropes & Gray 102 T6'wnsend Avenue 225 Franklin Street Boothbay Harber, Maine 04538
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Boston, Massachusetts 02110
' David Santee Miller, Esq.
Mr. Rufus E. Brown 213 Morgan Street, N. W.
Deputy Attorney General Washington, D. C.
20001 State of Maine Auguste,,pai ne 04330 Mr. Paul Swetland e r-q;.. -
Resident Tnspector/ Maine Yankee ~
Mr. Nicholas Barth c/o U.S.N.R.C.
Executive Director P. O. Box E Sheepscot Valley Conservation Wiscasset, Maine 04578 Association, Inc.
P. O. Box 125 Mr. Charles B. Brinkman Alan, Maine 04535 Manager - Washington Nuclear Operations Combustion Engineering Inc.
Wiscassett Public Library Association 4853 Cordell Avenue, Suite A-1
.High Street Bethesda, Maryland 20014 Wiscasset, Maine 04578 Mr. John H. Garrity, Director fir. Torbet H. Macdonald, Jr.
Nuclear Engineering & Licensing Office of Energy Resources Maine Yankee Atomic Power Company State House Station #53 Edison Drive Augusta, Maine 04333 Augusta, Maine 04336 Robert M. Lazo, Esq., Chairman Atonic Safety and Licensing Board U.S. Environmental Protection Agency U.S. Nuclear Regulatory Commi.ision Region 1 Office Washington, D. C.
20555 ATTH:
EIS COORDINATOR JFK Federal Building Dr. Cadet H. Hand, Jr., Director Boston,Massachgsetts 02203 Bodega Marine Laboratory University of California Bodega Bay, California 94923 Mr. Gustave A. Linenberger Atomic Safety and Liccn:ing Board State Planning Officer U.S. Nuclear Regulatory Commission Executive Department Washinaton, D. C.
20555 189 State Street Augusta, Maine 04330
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UNITED STATES o
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j NUCLEAR REGULATORY COMMISSION wasHtNGTON, D. C. 20$55 g
,p Cr'4j' SAFETY EVALUATION BY TPE OFFICE OF NUCLEAR REACTOR REGULATION FOR MAINE YANKEE ATOMIC POWER COMPANY MAINE YANKEE ATOMIC POWER STATION DOCKET NO. 50-309 -
~
~
' INTRODUCTION On March 28, 1979 the Three Mile Island Nuclear Power Plant, Unit 2 (TMI-2) experienced core damage which resulted from a series of events which were initiated by a loss of feedwater transient. Several aspects of the acci-dent have generic applicability at operating (enter NSSS) reactors. On Apr 1 IV,1919 IEyBulletin 79-06. was sent to all Combustion Engineering -
r rating plant licensees. The purpose of the Bulletin was to provide wformation concerning the accident at THI-2 and to request certain actions be taken by licensees to preclude a similar occurrence at their facilities. This bulletin was superseded and" expanded by IE Bulletin 79-06B dated April 14, 1979. By letters dated April 26, May 4 and 14, July 2 and August 10, 1979, Maine Yankee Atomic Power Company provided responses in conformance with the requirements of the Bulletins.
EVALUATION In the two year period since the Bulletin (s) have been implemented we have observed, in addition to our review of the responses enunerated above, that the licensee has complied with all the following provisions of the Bulletips:
- Understanding or the TMI-2 sequence of events.
- Review Plant Procedures for coping with accidents and transients.
- By review of procedures and training instructions:
(1) to avoid overriding automatic action of ESF, (2) to keep high_ pres'sure injection (HPI) system in operation for at least 20 minutes and to maintain 50 F subcooling margin, (3) to correlate HPI initiation with reactor coolant pump (RCP) opera-tion, and (4) to train operators not to rely on pressurizer level only, to deter-mine primary coolant inventory.
- Verification of emergency feedwater (EFW) valve positions and all safety-related valve positions to ensure proper operation of EFW and ESF.
4 n
..m n,
--- m.---
-. - * - ~
~
- By review of containment isolation initiation anii design for avoidance.of
. isolating lines that are needed to avoid degraded core cooling capability.
- By preparing and implementing procedures for all valves ehich could defeat or compromise flow of EFW.
- By reviewing operating mcdes and procedures to prevent inadvertent pumping of, radioactive gasses and liquids out of the primary containment.
- By reviewf ng procedures related to maintenance and test of safety-related systems to:
(1) verify operability of red, dant system prioF to removal of any system
~
from service, (2) varify operability of all systems followilig maintenance or testing, and (3) verification to operating personnel whenever a system is removed from or returned to service.
~ '
- By developing procedures and training operators to establish and maintain natural circulation.
.By tr'si'rIfiig'6pefators' to take ~into account reactor vessel integrity cont
~ ~
siderations during any accident or transient.
- By performing analyses and design modifications to reduce the likelihood of automatic PORY actuation during anticipated transients.
- By providing procedures and training operators for a prompt manual reactor trip for transients that result in a pressure increase in the reactor coolant system.
- By providing for prompt reporting within one hour of the time the reactor is not in a controlled.or expected condition of operation.
- By proposing any needed Technical Specification changes to implement any of the abcve parts of the Bulletins.
CONCLUSI0tl5 Based on our review of the information provided by the licensee in response to IE Bulletins, we conclude that the licensee has acceptably responded to these Bulletins. The~ actions taken by the licensee demonstrate its understanding of the concerns and implications of the TMI-2 accident as they relate to the Maine Yankee Atomic P.ower Station. These actions have resulted in added assurance for the continued protection of the public health and safety during plant operation.
l Dated: SEP 171981 l
l
I f3 0 j
unacu y
[o, UNITED STATES NUCLEAR REGULATORY COMMISSION y
s.,
g WASHINGTON, D. C. 20555 p
t,....,./
SEP 171981 Docket No. 50-309 Mr. Robert H. Groce Senior Engineer - Licensing Maine Yankee Atomi:: Power Company 1671 Worchester Road Framingham, Massachusetts 10701
Dear Mr. Groce:
We have completed a review of the information you have provide < in letters dated April 26, May 4 and 14, July ?. and August 10, 1979, in response to IE Bulletins 79-06 and 79-06B for the Maine Yankee Atomic Power Station. The enclosed Safety Evaluation addresses the completeness and, acceptability of the responses.
Your responses-to;;}E? Bulletin 79,t06C, regarding the operation of the reactor coolant pumps following a loss-of-coolant accident'will be reviewed separately as part of NUREG-0737 Item II.K.3.5.
The issuance of this evaluation completes Item II.K.1, IE Bulletins, f.r your facility.
Sincerely, 7.
Robert A. Clark, Chief Operating Reactors Branch #3 Division of Licensing s
Enclosure:
Safety Evaluation cc w/ enclosure:
See next page
~
Maine Yankee Atomic Power Company cc:
E. W. Thurlow, President Mrs.'L. Patricia Doyle, President Maine Yankee Atomic Power Company SAFE POWER FOR MAINE Edison Drive Post Office Box 774 Augusta, Maine 04336 Camden, Maine 04843 Mr. Donald E. Vandenburgh First Selectman of Wiscasset Vice President - Engineering Municipal Building Yankee Atomic Electric Company U. S. Route 1 20 Turnpike Road Wiscasset, Maine 04578 Westboro, Massachusetts 01581 Stanidy"R. Tupper, 'Esq.
~
John A. Ritsher, Esquire Tupper and Bradley Ropes & Gray 102 T6wnsend Avenue 225 Franklin Street Boothbay Harbor, Maine 04538 Boston, Massachusetts 02110
' David Santee Miller, Esq.
Mr. Rufils E. Brown 213 Morgan Street, N. W.
~
Deputy Attorney General Washington, D. C.
20001 State of Maine Augusta. p<aine 04330 Mr. Paul Swetland r
+;;r Resident Tnspector/ Maine Yanke f Mr. Nicholas Barth c/o U.S.N.R.C.
Executive Director P. O. Box C Sheepscot Valley Conservation Wiscasset, Maine 04578 Association, Inc.
P. O. Box 125 Mr. Charles B. Brinkman Alan, Maine 04535 Manager - Washington Nuclear Operations Combustion Engineering Inc.
Wiscassett Public Library Association 4853 Cordell Avenue, Suite A-1
.High Street Bethesda, Maryland 20014 Wiscase.at, Maine 04578 Mr. John H. Garrity, D.!ector Mr. Torbet H. Macdonald, Jr.
Nuclear Engineering & Licensing Office of Energy Resources Maine Yankee Atomic Power Company State House Station #53 Edison Drive Augusta, Maine 04333 Augusta, Maine 04336 Robert M. La::o, Esq., Chairman Atomic Safety and Licensing Board U.S. Environmental Protection Acency U.S. Nuclear Regulatory Commission Region I Office Washington, D. C.
20555 ATTH: EIS C0ORDINATOR JFK c deral Building e
Dr. Cadet H. Hand, Jr., Director Boe t:,.., Massachgsetts 02203 Bodega liarine Laboratory University of California Bodega Bay, Californi.a 94923 l
Mr. Gustava A. Linenberger l
Atomic Safety and Licensing Board State Planning Officer U.S. Nuclear Regulatory Commission Executive Department Washington, D. C.
20555 189 State Street Augusta, Maine 04330
c i'
ja* E8%9'o, UNITED STATES l'
NUCLEAR REGULATORY COMMISSION 3
.j WASHINGTON, D. C. 20555
\\7...+;/
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULCION FOR MAINE YANKEE ATOMIC POWER COMPANY MAINE YANKFE ATOMIC POWER STATION DOCKET NO. 50-309 -
~
INTRODUCTION On March 28, 1979 the Three Mile Iskand Nuclear Power Plant, Unit 2 (TMI-2) experienced core damage wnich resulted from a series of events which were initiated by a loss cf feedwater transient. Several aspects of the acci-dent have generic applicability at operating (enter NSSS) reactors. On April IV,'1919,4E-Bulletin 79-06. was sent to all Combustion Engineering -
i operating plant licensees. The purpose of the Bulletin was to provide information concerning the accident at TMI-2 and to request certain actions be taken & licensees to preclude a similar occurrence at their facilities. This bulletin was superseded a E expanded by IE Bulletin 79-06B dated April 14, 1979. By letters dated April 26, May 4 and 14, July 2,and August 10, 1979, Maine Yankee Atomic Power Company provided responses in conformance with the requirements of the Bulietins.
EVALUATION In the two year period since the Bulietin(s) hav'e been implemented we have observed, in addition to our review of the responses enumerated above, that the licensee has complied with all the following provisions of the Bulletins:
- Understanding of the TMI-2 sequence of events.
- Review Plant Procedures for coping with accidents and transients.
- By review of procedures and training instructions:
(1) to avoid overriding automatic action of ESF, (2) to keep high pres'sure injection (HPI) system in operation for at least 20 minutes and to maintain 50 F subcooling margin, (3) to correlate HPI initiation with reactor coolant pump (RCP) opera-l l
tion, and l
(4) to train operators not to rely on pressurizer level only, to deter-l mine primary coolant inventory.
- Verification of emergency feedwater (EFW) valve positions and all safety-related valve positions to ensure proper operation of EFW and ESF.
c j
. - By review of containment isolation initiation inii design for avoidance.of
~
isolating lines that are needed to avoid degraded core cooling capability.'
- By preparing and implementing procedures for all valves which could defeat or compromist flow of EFW.
- By reviewing operating modes and procedures to prevent inadvertent pumping of. radioactive gasses and liquids out of the primary containment.
- By reviewing procedures related to maintenance and test of safety-related systems to:
(1) verify operability of redundartt system prior to removal of any system
~
from service, (2) verify operability of all systems followfig maintenance or testing, and (3) verification to operating personnel whenever a system is removed from or returned to service.
~'
- By developing procedures and training operators to establish and maintain natural circulation.
- By trIirIfiif6pedt6is' to takeinto account reactoF vessel integrity cont siderations during any accident or transient.
- By performing analyses and design modifications to reduce the likelihood of automatic PORY actuation during anticipated transients.
- By providing procedures and training operators for a prcmpt manual reactor trip for transients that result in a pressure increase in the reactor coolant system.
- By providing for prompt reporting within one hour of the time the reactor is not in a controlled.or expected condition of operation.
- By proposing any needed Technical Specification changes to implement any of the above parts of the Bulletins.
CONCLUSIONS Based on our review of the information provided by the licensee in response to IE Bulletins, we conclude that the licensee has acceptably responded to these Bulletins. The' actions taken by the licensee demonstrate its understanding cf the concerns and implications of the TMI-2 accident as they relate to the Maine Yankee Atomic Power Station. These actions have resulted in added assurance for the continued protection of the public health and safety during plant operation.
Dated: SEP 171981 i
C gug
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UNITED STATES NUCLEAR REGULATORY COMMISSION g j {.v.( 3 g
g,' g ;f. E WASHINGTON, D. C. 20555
(&/
SEP 171981
+....
Docket No. 50-309 Mr. Robert H. Groce Senior Engineer - Licensing Maine Yankee Atomic Power Company 1671 Worchester Road Framingham, Massachusetts 10701
Dear Mr. Groce:
We have completed a review of the information you have provided in letters dated April 26, May 4 and 14, July 2 and August 10, 1979, in response to IE Bulletins 79-06 and 79-06B for the Maine Yankee Atomic Power S tation. The enclosed Safety Evaluation addresses the completeness and, acceptability of the responses.
Your responses!to;;}E4 Bulletin 79,.06C, regarding the -operation of the reactor coolant pumps following a loss-of-coolant accident will be reviewed separately as part of NUREG-0737 Item II.K.3.5.
The issuance of this evaluation completes Item II.K.1, IE Bulletins, for your facility.
Sincerely, 7
Robert A. Clark, Chief Operating Reactors Branch #3 Division of Licensing s
Enclosure:
Safety Evaluation cc w/ enclosure:
See next page 9
9 I
~~>
Maine Yankee Abmic Power Company j
cc:
E. W. Thurlow, President Mrs.'t. Patricia Doyle, Presid'ent Maine Yankee Atomic Power Company SAFE POWER FOR MAINE Edison Drive Post Office Box 774 Augusta, Maine 04336 Camden, Maine 04843 Mr. Donald E. Vandenburgh First Selectman of Wiscasset Vice President - Engineering Municipal Building Yankee Atomic Electric Company U. S. Route 1 20 Turnpike Road Wiscasset, Maine 04578 Westboro, Massachusetts 01581 Stanley 11. Tupper, "Esq.
John A. Ritsher, Esquire Tupper and Bradley Ropes & Gray 102 T6wnsend Avenue e
225 Franklin Street Boothbay Harbor, M ine 04538 Bosto.;, Massachusetts 02110
' David Santee Miller, Esq.
Mr. Rufus E. Brown 213 Morgan Street, N. W.
Deputy Attorney General Washington, D. C.
20001 State of Maine Augusta,Jaine 04330 Mr. Paul Swetland ers;;3-w - -
Resident Tnspector/ Maine Yankee-Mr. Nicholas Barth c/o U.S.N.R.C.
Executive Director P. O. Box E Sheepscot Valley Conservation Wiscasset, Maine 04578 Association, Inc.
P. O. Box 125 Mr. Charles B. Brinkman Alan, Maine 04535 Manager - Washington Nuclear Operations Combustion Engineering Inc.
Wiscassett Public Library Association 4853 Cordell Avenue, Suita A-1
.High Street Bethesda, Maryland 20014 Wiscasset, Maine 04578 Mr. John H. Garrity, Director Mr. Torbet H. Macdonald, Jr.
Nuclear Engineering & Licensing Office of Energy Resources Maine Yankee Atomic Power Company State House Station #53 Edison Drive Augusta, Maine 04333 Augusta, Maine 04336 Robert M. La::o, Esq., Chairman Atonic Safety and Licensing Board U.S. Environmental Protection Agency U.S. Nuclear Regulatory Commission Region I Office Washington, D. C.
20555 ATTN: EIS C00RNNATOR JFK Federal Building Dr. Cadet H. Hand, Jr., Director Boston,Massachgsetts 02203 Bodega liarine Laboratory University of California Bodega Bay, California 94923 Mr. Gustave. A. Linenberger Atomic Safety and Licensing Board State Planning Officer U.S. Nuclear Regulatory Commission Executive Department Washington, D. C.
20555 189 State Street Augusta, Maine 04330
[pn at %'o, UNITED STATES
[fp.,v,( ~]
NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555
- g{j% y S,.
u s, +~ p j
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION FOR MAINE YANKEE ATOMIC POWER COMPANY MAINE YANKEE ATOMIC POWER STATION DOCKET NO. 50-309 -
~
~.'
INTRODUCTION On March 28, 1979 the Three Mile Islar.d Nuclear Power Plant, Unit 2 (TMI-2) experienced core damage which resulted from a series of events which vere initiated by a loss of feedwater transient. Several aspects of the acci-dent have generic applicability at operating (enter NSSS) reactors. On April TV,'1919,4E;Bu11etin 79-06 was sent to all Combustion Engineering -
operating plant licensees. The purpose of the Bulletin was to provide information concerning the accident at TMI-2 and to request certain actions be taken by licensees to preclude a similar occurrence at their
+
facilities. This bulletin was superseded and" expanded by IE Bulletin 79-06B dated April 14, 1979. By letters dated April 26, May 4 and 14, July 2,and August 10, 1979, Maine Yankee Atomic Power Company provided responses in conformance with the requirements of the Bulletins.
EVALUATION In the two year period since the Bulletin (s) have been impicmented we have cbserved, in addition ta our review of the responses enunerated above, that the licensee has coolied with all the following provisions of the Bulletins:
Understanding of the '011-2 sequence of events.
Review Plant Procedures for coping with accidents and transients.
l 3y review of procedures and training instructions:
(1) to avoid overriding automatic action of ESF, (2) to keep high pressure injection (HPI) system in operation for at least 20 minutes and to maintain 50 F subcooling margin, (3) to correlate HPI initiation with reactor coolant pump (RCP) opera-tion, and (4) to train operators not to rely on pressurizer level only, to deter-mine primary coolant inventory.
Verification of emergency feedwater (EFW) valve positions and all safety-l related valve positions to ensure proper operation of EFW and ESF.
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, By review of containment' isolation initiation ind design for avoidance.of isolating lines that are needed to avoid degraded core cooling capability.
- By preparing and implementing procedures for all valves which could defeat or compromise flow of EFW.
- By reviewing operating modes and procedures to prevent inadvertent pumping of. radioactive gasses and liquids out of the primary containment.
- By reviewi.ng procedures related to maintenance and test of safety-related systems to:
(1) verify operability of redundartt system.prioF to removal of any system
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from service, (2) verify operability of all systems followiiig maintenance or testing, and (3) verification to operating personnel whenever a system is removed from or returned to service.
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- By developing procedures and training operators to establish and maintain natural circulation.
- By trit'rIfiig %psrit6rs' t6 take-into account reactor' vessel integrity cont siderations during any accident or transient.
- By performing analyses and design modifications to reduce the likelihood of automatic PORY actuation during anticipated transients.
- By providing procedures and training operators for a prompt manual reactor trip for transients that result in a pressure increase in the reactor coolant system.
- By providing for prompt reporting within one hour of the time the reactor is not in a controlled.or expected condition of operation.
- By proposing any needed Technical Specification changes to implement any of the above parts of the Bulletins.
C0t1CLUSI0t15 Based on our review of the information provided by the licensee in response to IE Bulletins, we conclude that the licensee has acceptably responded to these Bulletins. The' actions taken by the licensee demonstrate its understanding of the concerns and implications of the TMI-2 accident as they relate to the Maine Yankee Atomic Power Station. These actions have resulted in added assurance for the continued protection of the public health and safety during plant operation.
Dated: SEP 171981
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