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,1 New Hampshire , Tod C. .:..e - x a Senior Vice President and i Chieloperating C6cer l NYN-89136 ! | |||
,1 New Hampshire , Tod C. .:..e - x a | l November 1, 1989 J United. States Nuclear Regulatory Consnission Washington, DC 20555 ; | ||
Senior Vice President and i Chieloperating C6cer l NYN-89136 ! | |||
l November 1, 1989 J | |||
United. States Nuclear Regulatory Consnission Washington, DC 20555 ; | |||
Attention: Document Control Desk i | Attention: Document Control Desk i | ||
References (a) Facility Operating License No. NPF-67 Docket No. 50 443 ! | References (a) Facility Operating License No. NPF-67 Docket No. 50 443 ! | ||
(b) USNRC Generic Letter 88-20, dated November 23, 1989, I | (b) USNRC Generic Letter 88-20, dated November 23, 1989, I | ||
' Individual Plant Examination for Severe Accident Vulnerabilities' ; | ' Individual Plant Examination for Severe Accident Vulnerabilities' ; | ||
(c) Supplement 1 to USNRC Generic Letter 88-20, dated August i 29, 1989, ' Individual Plant Examination for Severe i Accident Vulnerabilities' I Subjects Response to Generic Letter 88-20 | (c) Supplement 1 to USNRC Generic Letter 88-20, dated August i 29, 1989, ' Individual Plant Examination for Severe i Accident Vulnerabilities' I Subjects Response to Generic Letter 88-20 | ||
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n The risk management process has two principal objectives. The first i | n The risk management process has two principal objectives. The first i | ||
: 3. objective is to maintain an updated probabilistic safety assessment for ' | : 3. objective is to maintain an updated probabilistic safety assessment for ' | ||
l ( [ Seabrook Station. Since completion of the SSPSA in 1983, many subject- > | l ( [ Seabrook Station. Since completion of the SSPSA in 1983, many subject- > | ||
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a comprehensive update of all aspects of the SSPSA was performed and i l | a comprehensive update of all aspects of the SSPSA was performed and i l | ||
D documented. The 1989 comprehensive update of the SSPSA is scheduled to be l l completed and documented by March 31, 1990. Updates consider, as r l appropriate, changes in plant design and operation and incorporate enhancements to the computer model employed to perform the analyses. | D documented. The 1989 comprehensive update of the SSPSA is scheduled to be l l completed and documented by March 31, 1990. Updates consider, as r l appropriate, changes in plant design and operation and incorporate enhancements to the computer model employed to perform the analyses. | ||
bsa.a. : | bsa.a. : | ||
i New Hampshire Yonkee Division of Public Service Company of New Hampshire pal P.O. Box 300 | i New Hampshire Yonkee Division of Public Service Company of New Hampshire pal P.O. Box 300 | ||
* Seabrook, NH 03874 | * Seabrook, NH 03874 | ||
* Telephone (603) 474 9521 g | * Telephone (603) 474 9521 g | ||
o ! | o ! | ||
i' United States Nuclear Regulatory Commission November 1, 1989 Attention: Document Control Desk Page 2 , | i' United States Nuclear Regulatory Commission November 1, 1989 Attention: Document Control Desk Page 2 , | ||
l | l Additionally, an in-depth study of the shutdown modes of operation 5 at i Seabrook Station, has effectively increased the scope of the SSPSA. j The second objective of the risk management process is to apply ' | ||
Additionally, an in-depth study of the shutdown modes of operation 5 at i Seabrook Station, has effectively increased the scope of the SSPSA. j | |||
The second objective of the risk management process is to apply ' | |||
probabilistic safety assessment information to proposed station design changes and improvements in methods of operation. A formal method, ! | probabilistic safety assessment information to proposed station design changes and improvements in methods of operation. A formal method, ! | ||
documented in NHY prccadures, implements this objective by requiring that significant plant changes are evaluated for their impact on the probabilistic -1 safety assessment. The results of the evaluation can indicate the need to i update the probabilistic safety assessment and/or revise the proposed change ! | documented in NHY prccadures, implements this objective by requiring that significant plant changes are evaluated for their impact on the probabilistic -1 safety assessment. The results of the evaluation can indicate the need to i update the probabilistic safety assessment and/or revise the proposed change ! | ||
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and associated studies, plus the 1989 update described above. The 23PSA was, : | and associated studies, plus the 1989 update described above. The 23PSA was, : | ||
and thus the IPE will be, a full-scope, level three probabilistic safety l assessment. As a full-scope probabilistic safety assessment, the SSPSA l included consideration of both internal transients and external hazardo as ' | and thus the IPE will be, a full-scope, level three probabilistic safety l assessment. As a full-scope probabilistic safety assessment, the SSPSA l included consideration of both internal transients and external hazardo as ' | ||
l initiating events that could potentially cause a severe accident. As a level l three probabilistic safety assessment, the SSPSA evaluates potential accident | l initiating events that could potentially cause a severe accident. As a level l three probabilistic safety assessment, the SSPSA evaluates potential accident | ||
* sequences beginning with the initiating event and including plant operator response, potential core damage, fission product release and offsite . | * sequences beginning with the initiating event and including plant operator response, potential core damage, fission product release and offsite . | ||
consequences. | consequences. | ||
New Hampshire Yankee will submit a report describing the IPE by March 1, 1991. This report will sunanarize the SSPSA, its associated studies and the , | New Hampshire Yankee will submit a report describing the IPE by March 1, 1991. This report will sunanarize the SSPSA, its associated studies and the , | ||
current comprehensive update. The report will include a cross-reference to , | current comprehensive update. The report will include a cross-reference to , | ||
relate sections of the report to the corresponding format defined in NUREG- ^ | relate sections of the report to the corresponding format defined in NUREG- ^ | ||
l 1335. , | l 1335. , | ||
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l If you have any questions on this matter, please contact Mr. Geoffrey i Kingston at (603) 474-9521, extension 3371. | l If you have any questions on this matter, please contact Mr. Geoffrey i Kingston at (603) 474-9521, extension 3371. | ||
Sincerely yours, hlb Ted C. Feigenbaum , | Sincerely yours, hlb Ted C. Feigenbaum , | ||
, United States Nuclear Regulatory Commission November 1, 1989 Attention: Document Control Desk Page 3 cci Mr. V1111am T. Russell Regional Administrator United States Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 | , United States Nuclear Regulatory Commission November 1, 1989 Attention: Document Control Desk Page 3 cci Mr. V1111am T. Russell Regional Administrator United States Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 | ||
~ | ~ | ||
Mr. Victor Herses, Project Manager Project Directorate I-3 United States Nuclear Regulatory Conunission Diviston of Reactor Projects Washington, DC 20555 Mr. Dave Modeon Nuclear Management and Resources Council 1776 Eye Street, N.W. | Mr. Victor Herses, Project Manager Project Directorate I-3 United States Nuclear Regulatory Conunission Diviston of Reactor Projects Washington, DC 20555 Mr. Dave Modeon Nuclear Management and Resources Council 1776 Eye Street, N.W. | ||
Suite 300 Washington, DC 20006-2496 Mr. Antone C. Cerne NRC Senior Resident Inspector P. O. Box 1149 Seabrook, NH 03874 I | Suite 300 Washington, DC 20006-2496 Mr. Antone C. Cerne NRC Senior Resident Inspector P. O. Box 1149 Seabrook, NH 03874 I | ||
STATE OF NEW HAMPSHIRE | STATE OF NEW HAMPSHIRE Rockingham, ss. November 1, 1989 l Then personally appeared before me, the above named Ted C. Feigenbaum who, being duly sworri, did state that he is Senior Vice President and Chief ; | ||
Rockingham, ss. November 1, 1989 l Then personally appeared before me, the above named Ted C. Feigenbaum who, being duly sworri, did state that he is Senior Vice President and Chief ; | |||
Operating Officer of New Hampshire Yankee, that he is duly authorized to i execute and file the foregoing information in the name and on the behalf of l New Hampshire Yankee, and that the statements therein are true to be the ; | Operating Officer of New Hampshire Yankee, that he is duly authorized to i execute and file the foregoing information in the name and on the behalf of l New Hampshire Yankee, and that the statements therein are true to be the ; | ||
best of his knowledge and belief. i OMu O S M e wo ., ! | best of his knowledge and belief. i OMu O S M e wo ., ! | ||
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Hy Commission Expires: March 6, 1990 i | Hy Commission Expires: March 6, 1990 i | ||
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New Hampshire Yankee [ | New Hampshire Yankee [ | ||
November 1, 1989 l t, | November 1, 1989 l t, | ||
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ENCLOSURE 1 TO NYN-89136 i | ENCLOSURE 1 TO NYN-89136 i | ||
I RESPONSE TO GENERIC LETTER 88-20 ; | I RESPONSE TO GENERIC LETTER 88-20 ; | ||
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e- | e-ENCLOSURE 1 TO NYN-89136 ADDITIONAL REFERENCES ASSOCIATED VITH THE SSPSA | ||
ENCLOSURE 1 TO NYN-89136 ADDITIONAL REFERENCES ASSOCIATED VITH THE SSPSA | |||
: 1. Pickard, Lowe and Garrick Inc., 'Seabrook Station Probabilistic Safety Assessment', prepared for Public Service Company of New Hampshire and the Yankee Atomic Electric Company PLG-0300 December, 1983. | : 1. Pickard, Lowe and Garrick Inc., 'Seabrook Station Probabilistic Safety Assessment', prepared for Public Service Company of New Hampshire and the Yankee Atomic Electric Company PLG-0300 December, 1983. | ||
l | l | ||
: 2. DeVincentis, J., Public Service Company of New Hampshire, letter to i the NRC, SBN-617. January 30, 1984. ! | : 2. DeVincentis, J., Public Service Company of New Hampshire, letter to i the NRC, SBN-617. January 30, 1984. ! | ||
: 3. NUREG/CR-4452, ' Review of Relap 5 Calculations for H. B. Robinson, 5 | : 3. NUREG/CR-4452, ' Review of Relap 5 Calculations for H. B. Robinson, 5 Unit II Pressurized Thermal Shock Study', December 1985. | ||
Unit II Pressurized Thermal Shock Study', December 1985. | |||
: 4. NUREG/CR-4540, 'A Review of the Seabrook Station Probabilistic Safety ' | : 4. NUREG/CR-4540, 'A Review of the Seabrook Station Probabilistic Safety ' | ||
As s e s smer.t Containment Failure Modes and Radiological Source Terms'. Brookhaven National Laboratory, February 1986. ' | As s e s smer.t Containment Failure Modes and Radiological Source Terms'. Brookhaven National Laboratory, February 1986. ' | ||
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, Emergency Planning Study', Pickard, Lowe and Garrick Inc., PLG-0432 L | , Emergency Planning Study', Pickard, Lowe and Garrick Inc., PLG-0432 L | ||
o prepared for New Hampshire Yankee Division, Public Service Company of I New Hampshire December 1985. ' | o prepared for New Hampshire Yankee Division, Public Service Company of I New Hampshire December 1985. ' | ||
: 9. Fleming, K. N., et al, 'Seabrook Station Emergency Planning . | : 9. Fleming, K. N., et al, 'Seabrook Station Emergency Planning . | ||
Sensitivity Study', Pickard, Lowe and Garrick, Inc., PLG-0465, l prepared for Public Service Company of New Hampshire, April 1986. , | Sensitivity Study', Pickard, Lowe and Garrick, Inc., PLG-0465, l prepared for Public Service Company of New Hampshire, April 1986. , | ||
: 10. Fleming, K. N. and A. Torri, ' Risk Management Actions to Assure | : 10. Fleming, K. N. and A. Torri, ' Risk Management Actions to Assure Containment Effectiveness at Seabrook Station', Pickard, Lowe and Garrick, Inc., prepared for New Hampshire Yankee Division, Public ' | ||
Containment Effectiveness at Seabrook Station', Pickard, Lowe and Garrick, Inc., prepared for New Hampshire Yankee Division, Public ' | |||
Service Company of New Hampshire PLG-0550, July 1987. t l | Service Company of New Hampshire PLG-0550, July 1987. t l | ||
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Revision as of 01:31, 1 February 2020
ML19325E586 | |
Person / Time | |
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Site: | Seabrook |
Issue date: | 11/01/1989 |
From: | Feigenbaum T PUBLIC SERVICE CO. OF NEW HAMPSHIRE |
To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
References | |
RTR-NUREG-1335, RTR-NUREG-CR-4452, RTR-NUREG-CR-4540 GL-88-20, NYN-89136, NUDOCS 8911080055 | |
Download: ML19325E586 (5) | |
Text
~~
,1 New Hampshire , Tod C. .:..e - x a Senior Vice President and i Chieloperating C6cer l NYN-89136 !
l November 1, 1989 J United. States Nuclear Regulatory Consnission Washington, DC 20555 ;
Attention: Document Control Desk i
References (a) Facility Operating License No. NPF-67 Docket No. 50 443 !
(b) USNRC Generic Letter 88-20, dated November 23, 1989, I
' Individual Plant Examination for Severe Accident Vulnerabilities' ;
(c) Supplement 1 to USNRC Generic Letter 88-20, dated August i 29, 1989, ' Individual Plant Examination for Severe i Accident Vulnerabilities' I Subjects Response to Generic Letter 88-20
+
Gentlemen:
In response to Reference (b), this letter provides information l pertaining'to the New Hampshire Yankee (NHY) Program for performing the ;
Individual Plant Examination (IPE) for Seabrook Station. In summary, NNY j has already fulfilled the intent of Generic Letter 88-20 to ' perform a {
systematic examination to identify any plant-specific vulnerabilities to }
severe accidents *.
Station Probabilistic ThishasbeenaccomplishedbycompletionoftheSeabrook
Safety Assessment (SSPSA) and the establishment of an l
' ongoing risk management process.
l t
The SSPSA was completed in 1983 by a team of offsite contractors led I by Pickard, Lowe and Garrick, Inc., with significant input from NHY and i Yankee Atomic Electric Company (YAEC). The SSPSA is a full-scope, level i three probabilistic safety assessment applicable specifically to Seabrook
- Station. It was submitted to NRC for information on January 30, 1984.2 NRC i l reviews of the SSPSA are documented in two NRC reports: NUREG/CR-44523 and ppm NUREG/CR-4540.4 }
hau ,
n The risk management process has two principal objectives. The first i
- 3. objective is to maintain an updated probabilistic safety assessment for '
l ( [ Seabrook Station. Since completion of the SSPSA in 1983, many subject- >
it ;" specific updates of the SSPSA have been performed and documented. In 1986, !
l' -
a comprehensive update of all aspects of the SSPSA was performed and i l
D documented. The 1989 comprehensive update of the SSPSA is scheduled to be l l completed and documented by March 31, 1990. Updates consider, as r l appropriate, changes in plant design and operation and incorporate enhancements to the computer model employed to perform the analyses.
bsa.a. :
i New Hampshire Yonkee Division of Public Service Company of New Hampshire pal P.O. Box 300
- Seabrook, NH 03874
- Telephone (603) 474 9521 g
o !
i' United States Nuclear Regulatory Commission November 1, 1989 Attention: Document Control Desk Page 2 ,
l Additionally, an in-depth study of the shutdown modes of operation 5 at i Seabrook Station, has effectively increased the scope of the SSPSA. j The second objective of the risk management process is to apply '
probabilistic safety assessment information to proposed station design changes and improvements in methods of operation. A formal method, !
documented in NHY prccadures, implements this objective by requiring that significant plant changes are evaluated for their impact on the probabilistic -1 safety assessment. The results of the evaluation can indicate the need to i update the probabilistic safety assessment and/or revise the proposed change !
to enhance safety. In addition to reviews of proposed changes. NNY has also applied probabilistic safety assessment information to Technical Specification .
i optimization 7and emergency planning strategies.8,9,10 Personnel experienced in probabilistic risk assessment methods onsite and at YAEC implement the risk '
management process for Seabrook Station. l The Individual Plant Examination (IPE) for severe accident vulnera- ,
bilities at Seabrook Station will consist of the previously submitted SSPSA ~
and associated studies, plus the 1989 update described above. The 23PSA was, :
and thus the IPE will be, a full-scope, level three probabilistic safety l assessment. As a full-scope probabilistic safety assessment, the SSPSA l included consideration of both internal transients and external hazardo as '
l initiating events that could potentially cause a severe accident. As a level l three probabilistic safety assessment, the SSPSA evaluates potential accident
- sequences beginning with the initiating event and including plant operator response, potential core damage, fission product release and offsite .
consequences.
New Hampshire Yankee will submit a report describing the IPE by March 1, 1991. This report will sunanarize the SSPSA, its associated studies and the ,
current comprehensive update. The report will include a cross-reference to ,
relate sections of the report to the corresponding format defined in NUREG- ^
l 1335. ,
Enclosure 1 lists additional references associated with the SSPSA.
l If you have any questions on this matter, please contact Mr. Geoffrey i Kingston at (603) 474-9521, extension 3371.
Sincerely yours, hlb Ted C. Feigenbaum ,
, United States Nuclear Regulatory Commission November 1, 1989 Attention: Document Control Desk Page 3 cci Mr. V1111am T. Russell Regional Administrator United States Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406
~
Mr. Victor Herses, Project Manager Project Directorate I-3 United States Nuclear Regulatory Conunission Diviston of Reactor Projects Washington, DC 20555 Mr. Dave Modeon Nuclear Management and Resources Council 1776 Eye Street, N.W.
Suite 300 Washington, DC 20006-2496 Mr. Antone C. Cerne NRC Senior Resident Inspector P. O. Box 1149 Seabrook, NH 03874 I
STATE OF NEW HAMPSHIRE Rockingham, ss. November 1, 1989 l Then personally appeared before me, the above named Ted C. Feigenbaum who, being duly sworri, did state that he is Senior Vice President and Chief ;
Operating Officer of New Hampshire Yankee, that he is duly authorized to i execute and file the foregoing information in the name and on the behalf of l New Hampshire Yankee, and that the statements therein are true to be the ;
best of his knowledge and belief. i OMu O S M e wo ., !
Beverly E.dilloway, Notary Pjblic !
Hy Commission Expires: March 6, 1990 i
i l
9
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New Hampshire Yankee [
November 1, 1989 l t,
i I
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I h
I i
ENCLOSURE 1 TO NYN-89136 i
I RESPONSE TO GENERIC LETTER 88-20 ;
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e-ENCLOSURE 1 TO NYN-89136 ADDITIONAL REFERENCES ASSOCIATED VITH THE SSPSA
- 1. Pickard, Lowe and Garrick Inc., 'Seabrook Station Probabilistic Safety Assessment', prepared for Public Service Company of New Hampshire and the Yankee Atomic Electric Company PLG-0300 December, 1983.
l
- 2. DeVincentis, J., Public Service Company of New Hampshire, letter to i the NRC, SBN-617. January 30, 1984. !
- 3. NUREG/CR-4452, ' Review of Relap 5 Calculations for H. B. Robinson, 5 Unit II Pressurized Thermal Shock Study', December 1985.
- 4. NUREG/CR-4540, 'A Review of the Seabrook Station Probabilistic Safety '
As s e s smer.t Containment Failure Modes and Radiological Source Terms'. Brookhaven National Laboratory, February 1986. '
- 5. Kiper, K. L., T. J. Casey, and W. Dookocil, 'Seabrook Station i Probabilistic Safety Study-Shutdown Modes 4, 5 and 6, prepared for i New Hampshire Yankee Division Public Service Company of New ;
Hampshire, May 1988. '
- 6. New Hampshire Yankee Engineering Procedure No. 35010, ' Safety / ;
Reliability Review of Plant Changes', effective December 13, 1988.
I
- 7. Pickard, Lowe and Garrick, Inc., ' Risk-Based evaluation of Technical -
Specifications for Seabrook Station', prepared for New Hampshire ,
Yankee Division. Public Service Company of New Hampshire, PLG-0451, l August 1985. ,
t L 8. Fleming K. N., et al, 'Seabrook Station Risk Management and
, Emergency Planning Study', Pickard, Lowe and Garrick Inc., PLG-0432 L
o prepared for New Hampshire Yankee Division, Public Service Company of I New Hampshire December 1985. '
- 9. Fleming, K. N., et al, 'Seabrook Station Emergency Planning .
Sensitivity Study', Pickard, Lowe and Garrick, Inc., PLG-0465, l prepared for Public Service Company of New Hampshire, April 1986. ,
- 10. Fleming, K. N. and A. Torri, ' Risk Management Actions to Assure Containment Effectiveness at Seabrook Station', Pickard, Lowe and Garrick, Inc., prepared for New Hampshire Yankee Division, Public '
Service Company of New Hampshire PLG-0550, July 1987. t l
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