ML20150B324: Difference between revisions
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| number = ML20150B324 | | number = ML20150B324 | ||
| issue date = 10/20/1978 | | issue date = 10/20/1978 | ||
| title = Responds to | | title = Responds to Re Requirements for Cold Shutdown. Further Clarification,Based on Discussions W/B&W & Staff Position on Requirements for Seismic Category 1 Fuel Bldg & Mod Required Encl | ||
| author name = Vassallo D | | author name = Vassallo D | ||
| author affiliation = NRC OFFICE OF NUCLEAR REACTOR REGULATION (NRR) | | author affiliation = NRC OFFICE OF NUCLEAR REACTOR REGULATION (NRR) | ||
Line 11: | Line 11: | ||
| contact person = | | contact person = | ||
| document report number = NUDOCS 7811010189 | | document report number = NUDOCS 7811010189 | ||
| title reference date = 05-29-1978 | |||
| document type = CORRESPONDENCE-LETTERS, NRC TO UTILITY, OUTGOING CORRESPONDENCE | | document type = CORRESPONDENCE-LETTERS, NRC TO UTILITY, OUTGOING CORRESPONDENCE | ||
| page count = 9 | | page count = 9 | ||
Line 23: | Line 24: | ||
==Dear Mr. Berry:== | ==Dear Mr. Berry:== | ||
SUBJ ECT: REQUIREMENTS FOR COLD SHUTDOWN AND SEISMIC CATEGORY I FUEL BUILDING FOR GREENE COUNTY NUCLEAR POWER PLANT In a letter dated May 29, 1978, we transmitted to the Power Authority of the State of New York our position on the design requirements for capability to achieve cold shutdown relative to the Greene County Nuclear Power Plant (Reactor Systems Branch 212.89). Since that position was issued to the Power Authority, we have had several discussions with Babcock and Wilcox regarding cold shutdown. Based on these discussions, we have clarified our earlier position and this clarification is provided in Enclosure 1. | SUBJ ECT: REQUIREMENTS FOR COLD SHUTDOWN AND SEISMIC CATEGORY I FUEL BUILDING FOR GREENE COUNTY NUCLEAR POWER PLANT In a {{letter dated|date=May 29, 1978|text=letter dated May 29, 1978}}, we transmitted to the Power Authority of the State of New York our position on the design requirements for capability to achieve cold shutdown relative to the Greene County Nuclear Power Plant (Reactor Systems Branch 212.89). Since that position was issued to the Power Authority, we have had several discussions with Babcock and Wilcox regarding cold shutdown. Based on these discussions, we have clarified our earlier position and this clarification is provided in Enclosure 1. | ||
I 1 In the SER Supplement No. 1, we noted that a portion of the fuel building is not designated a seismic Category I structure. In order to clarify our requirements on this item, the NRC staff position is provided in Enclosure 2. | I 1 In the SER Supplement No. 1, we noted that a portion of the fuel building is not designated a seismic Category I structure. In order to clarify our requirements on this item, the NRC staff position is provided in Enclosure 2. | ||
We request that you commit to modifying your design to conform with these positions. We find that these matters must be resolved prior to the issuance of the final Supplement to the Safety Evaluation Report. | We request that you commit to modifying your design to conform with these positions. We find that these matters must be resolved prior to the issuance of the final Supplement to the Safety Evaluation Report. |
Latest revision as of 10:46, 11 December 2021
ML20150B324 | |
Person / Time | |
---|---|
Site: | Green County ![]() |
Issue date: | 10/20/1978 |
From: | Vassallo D Office of Nuclear Reactor Regulation |
To: | Berry G POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK |
References | |
NUDOCS 7811010189 | |
Download: ML20150B324 (9) | |
Text
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.j @ rec I /\g u ' UNITED STATES y ,, , NUCLEAR REGULATORY COMMISSION s" g $ WASHINGTON, D. C. 20555
{ z 007 2 0 1978 k . . . . . ,,/
Docket No. 50-549 Mr. George T. Berry General Manager & Chief Engineer Power Authority of the State of New York 10 Columbus Circle New York, New York 10019
Dear Mr. Berry:
SUBJ ECT: REQUIREMENTS FOR COLD SHUTDOWN AND SEISMIC CATEGORY I FUEL BUILDING FOR GREENE COUNTY NUCLEAR POWER PLANT In a letter dated May 29, 1978, we transmitted to the Power Authority of the State of New York our position on the design requirements for capability to achieve cold shutdown relative to the Greene County Nuclear Power Plant (Reactor Systems Branch 212.89). Since that position was issued to the Power Authority, we have had several discussions with Babcock and Wilcox regarding cold shutdown. Based on these discussions, we have clarified our earlier position and this clarification is provided in Enclosure 1.
I 1 In the SER Supplement No. 1, we noted that a portion of the fuel building is not designated a seismic Category I structure. In order to clarify our requirements on this item, the NRC staff position is provided in Enclosure 2.
We request that you commit to modifying your design to conform with these positions. We find that these matters must be resolved prior to the issuance of the final Supplement to the Safety Evaluation Report.
I
! If you have any questions with regard to these positions, please contact us.
j Singerely,
\
I bik d Ah NH.
DY B. Vass lib, Assidtant g yirector for Light Water Reac ors i DivisionofProjectMa} nag # ment
Enclosures:
As Stated CCs W/ enclosures:
See next pages
~M/O/D I69
e e i Mr. George T. Berry I
General Manager & Chief Engineer l
Power Authority of the State of New York 10 Columbus Circle New York, New York 10019 l
cc: Admiral P. J. Early Power Authority of the State of New York 10 Columbus Circle New York, New York 10019 Mr. Andrew W. Barchas Project Engineer Power Authority of the State of New York 10 Columbus Circle New York, New York 10019 Director, Technical Development Programs State of New York Energy Office Agency Building 2 Empire State Plaza Albany, New York 12223 Gregory F. Golgowski Planning Aide Colurbia County Environmental Management Council 247 Warren Street Hudson, New York 12534 I Mr. W. C. Gruenberg, Jr. ,
I Project Engineer Stone & Webster Engineering Corporation Post Office Box 1350 4 New York, New York 10001 Mr. S. F. Hellman, Project Manager Babcock & Wilcox Company Post Office box 1260 Lynchburg, Virginia 24505 Mr. P. W. Lyon Manager-Nuclear Operations Power Authority of the State of New York 10 Columbus Circle New York, New York 10019 o _ _ _ _ _ _ _ _ _ _ - - _
Mr. George T. Berry - -
cc: Algird F. White, Jr.
- DeGraff, Foy, Conway and
} Holt-Harris I Attorneys and Counselors at Law l Ninety State Street j
Albany, New York 12207 Jeffrey C. Cohen, Esq.
New York State Energy Office i Swan Street Building ,
l Core 1 - 2nd Floor Empire State Plaza Albany, New York 12223 l
Arthur Rheingold, Esq.
Assistant General Counsel Mark S. Kahan, Esq.
Staff Counsel State of New York Public Service Commission
- Empire State Plaza l Albany, New York 12223 ,
Lewis R. Bennett, Esq.
Assistant General Manager - General Counsel Power Authority of the State of New York ,
10 Columbus Circle New York, New York 10019 Vito J. Cassan, Esq.
Assistant General Counsel Power Authority of the State of New York 10 Columbus Circle New York, New York 10019 Edward R. Patrick, Esq.
i Assistant Counsel for Energy l NYS Department of Environmental i Conservation i
Room 608 - 50 Wolf Road Albany, New York 12233
I Mr. George T. Berry - -
l cc: Mid-Hudson Nuclear Opponents
- P. O. Box 666
! New Paltz, New York 12561 Ms. Rosemary S. Pooler Executive Director New York State Consumer Protection Board 99 Washington Avenue Albany, New York 12210 Citizens to Preserve the Hudson Valley c/o Robert J. Kafin, Esq.
Glens Falls, New York 12801 Albert K. Butzel, Esq.
Butzel & Kass 45 Rockefeller Plaza, Suite 2350 New York, New York 10020 Edward W. Hyland, Vice President General Counsel and Secretary Lehigh Portland Cement Company 718 Hamilton Mall Allentown, Pennsylvania 18105 William J. Spampinato, Esq.
Rosenberg & Spampinato 443 Warren Street Hudson, New Y;rk 12534 l Arthur L. Reuter, Esq.
j Attorney at Law
., Sharpe's Landing Germantown, New York 12526 l Mr. John Nickolitch
.j Cementon Civic Association P. O. Box 124 Cementon, New York 12415 l
l .
Mr. George T. Berry - -
i cc: Nancy Spiegel, Esq.
NYS Public Service Commission Agency Building 3 Empire cate Plaza Albany, New York 12223 Andrew C. Goodhope, Esq., Chairman li Atomic Safety and Licensing Board 3320 Estelle Terrace Wheaton, Maryland 20906 l Dr. Richard F. Cole i Atomic Safety and Licensing Board
- U. S. Nuclear Regulatory Comaission i
Washington, D. C. 20555 Dr. George A. Ferguson Professor of Nuclear Engineering Howard University Washington, D. c. 20666 l
ENCLOSURE 1 007 2 0 1978
?' .
_210 REACTOR SYSTEMS BRANCH Request for Additional Information Greene County i For each part of our cold shutdown position, clarification, if necessary, is provided as follows:
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Provide safety-grade steam generator dump valves, operators, air and pouer supplies which meet the single failure criterion.
i The staff position is that, for applications not yet docketed, local manual f
! operation of the MADV's will not be acceptable, except to mitigate the consequences of a single active failure. Operation from the control room, for the time necessary to cool the plant to initiation of the decay heat removal system, will be required. Local manual operation, if necessary, would be approved for dump valves in plants now under construction and for active applications for which an SER has been written. Justification for
, the acceptability of local operation must include actual local test I
- - operation of the MADV's, showing that the plant can be cooled in a controlled I
l manner and that the MADV's can be operated safely and effectively. It is i
assumed that the valve body, etc., is designed to seismic Category I I requirements and that manual operation could be achieved following a safe
! shutdown earthquake.
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6 Provide the capability to cool down to cold shutdcun in less than l
36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />, assuming the most limiting single failure and uith only offsite or onsite pouer available, or shou that manual actions inside e
or outside containment or return to hot standby until the manual l; actions or maintenance can be perfomed to correct the failure
/ provides an acceptable alternative.
r .
i h The staff now requires that assuming the most limiting single failure, with h only offsite or onsite power available and a safe shutdown earthquake,
- 5. capability must exist to cool down to the decay heat removal system cut-in L
conditions (rather than cold shutdown) in approximately 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
~~
007 2 0 1978 I .
The staff position is that the current heat removal capacity is inadequate I
- if this criterion can not be met. B&W's calculations for Erie indicate
(
that if one of the two available MAD valves is mechanically stuck closed, l
the plant cooldown time would be extended to at least several days. The ~
[ staff considers this time excessive. Accordingly, we require that additional cooldown capability be provided. The addition of two MADV's l (one per steam generator) with the same capacity as the original valves would be an acceptable approach. .
l .
Provide the capability to depressurize the reactor coolant system l vith only safety-grade systems assicning a single failure and with only offsite or onsite power available or shou that manual actions
, inside or outside containment or remaining at hot standby until
- marmal actions or repairs are complete provides an acceptable 1 alternative.
i l'
Provide the capability for boration with only safety-grade systems asstening a single failure and with only offs *te or onsite power available, or shou that manual actions inside or outside containment or remaining at hot standby until manual action or repairs are l completed provides an acceptable alternative.
The staff considers it acceptable to stay at hot shutdown for the time necessary to correct single failures, provided the overall cooldown time to reach DHR cut-in conditions is approximately 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />. In providing the capability to depressurize and borate the reactor coolant system, i
assuming a single failure and loss of offsite power, local operator action will be permitted to correct failures, if shown to be acceptable (including consideration of accessibility of required equipment). Availability of nonsei::mic Category I equipment may not be assumed.
b The. staff requires that the highest worth control rod is assumed at the
, fully withdrawn position when considering boration requirements.
}.: ,
e 4
- x. *
- , . OM 2 0 1978 Conduct or reference approved prototype qualification tests to study the mi=ing of the added borated water and the cooldoon under natural circulation conditions with a worst-case single failure (i.e., a i
single failure of a steam generator atmospheric dump valve). These tests and analyses vill be used to obtain information on cooldoun _
times and the corresponding auxiliary feedvater requirements.
t A single prototype qualification test on the lead plant of a given design I is acceptable. However, other tests might be required due to differences in system or component arrangement, procedural differences, new questions f concerning accessibility or safety for manual actions, or other concerns not addressed by the initial prototype test.
P 3
Provide specific procedures, at the operating license review stage, for cooling doun using natural circulation, and submit a summary outline of these procedures during the construction permit revieu.
Provide or require a seismic Category I auxiliary feeduater supply for at least four hours at hot shutdoun plus cooldoun to the de cy heat removal systen cut-in based on the longest time (for only l
onsite or offsite power and asswning the vorst single failure),
i or shou that an adequate alternate seismic Category I source vill I be available.
1 Meetings with Babcock and Wilcox did not indicate that clarification of these parts of our position was necessary.
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T-P
7..---..
OCI 2 0 1970 ENCLOSURE 2 010 AUXILIARY SYSTEMS BRANCH i
j 011.26 The applicant shall redesign the non-seismic Category I l portions of the fuel building (designated as such in the PSAR) to seismic Category I requirements. In doing so, the applicant shall assure that all portions of the structure and systems which serve as a low leakage barrier to provide atmospheric isolation of the spent fuel storage pool and associated fuel handling area are designed to seismic Category I criteria. -
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