ML17037B577
| ML17037B577 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 09/10/1975 |
| From: | Lear G Office of Nuclear Reactor Regulation |
| To: | Rhode G Niagara Mohawk Power Corp |
| References | |
| Download: ML17037B577 (10) | |
Text
0 Docket No. 50-220 Niagara Mohawk Power Corporation ATTN:
Mr. Gerald K. Rhode Vice President Engineering 300 Erie Boulevard Nest
- Syracuse, New York 13202 DISCI'RIBUTION:
5AC PDR Gray file Lo/al PDR Wocket ORB83 Rdg KRGoller TJCarter
'Lear JGuibert SATeets OELD 015E (3)
TBAbernathy SVarga DEisenhut Gentlemen:
ACRS (16)
RWoods A preliminary review of your applications for license amendments dated Juno 30, 1975 and August 18, 1975 indicated that wo will require additional information.
The 'requested information is c'ontainod in the enclosure.
In order that we may complete our review on a timely basis and accommodate your earliest anticipated Cycle 4 startup date of November 1, 1975, please submit your written response to the items contained in the enclosure within 14 days following receipt of this letter.
If you have any questions regarding tho requested information, we would be pleased to meet with you.
Sincerely,
/s/
Georgo Lear, Chief Operating Reactors Branch 83 Division of Reactor Licensing
Enclosure:
Requested Information on HCCS
'and GETAB Analyses for Nine Mile Point Unit 1 cc:
Seo noxt pago orrlcc~
CVRNAMC~
DATC+
3 TR Q
JG ert:kmf RNoods 9/ 'I
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/75 ORBS3 GLear FOrm hEC.318 (ROT. 9.f3) hXCM 0240 4 U, 0, OOVCllNMCNTrtllNTINOOrrICCI 107A 020 100
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Niagara Mohawk Power Corporation SEP 1
0 3975 CC:
Arvin E. Upton, Esquire
- LeBoeuf, Lamb, Leiby $ MacRae 1757 N Street, N.
W.
Washington, D. C.
20036 Anthony Z. Roisman, Esquire Berlin, Roisman 5 Kessler 1712 N Street, N.
W.
Washington, D. C.
20036 Dr. William Seymour, Staff Coordinator New York State Atomic Energy Council New York State Department of Commerce 112 State Street
- Albany, New York 12207 Oswego City Library 120 E. Second Street Oswego,.
New York 13126
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UN!TED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, O.
C. 20555 Docket No. 50-220 SEP1 O 8]5 Niagara hIohawk Power Corporation ATl'N:
Mr. Gerald K. Rhode Vice President
- Engineering 300 Erie Boulevard West
- Syracuse, New York 13202 Gentlemen:
A preliminary review of your applications for license amendments dated June 30, 1975 and August 18, 1975 indicated that we will require additional information.
The requested information is contained in the enclosure.
In order that we may complete our review on a timely basis and accommodate your earliest anticipated Cycle 4 startup date of November 1, 1975, please submit your written response to the items contained in the enclosure within 14 days following receipt of this letter.
If you have any questions regarding the requested information, we would be pl'eased to meet with you.
Sincerely,
~ George Lea
, Chief Operating Reactors Branch 83 Division of Reactor Licensing
Enclosure:
Requested Information on ECCS and GETAB Analyses for Nine Mile Point Unit 1 cc:
See next page
~'
J r
Niagara Mohawk Power Corporation SEP 1 0
@75 CC:.
Arvin E. Upton, Esquire
- LeBoeuf, Lamb, Leiby $ MacRae 1757 N Street, N.
W.
Washington, D. C.
20036 Anthony Z. Roisman, Esquire Berlin, Roisman 5 Kessler 1712 N Street, N.
W.
Washington, D. C.
20036 Dr. William Seymour, Staff Coordinator New York State Atomic Energy Council New York State Department of Commerce 112 State Street Albany,. New York 12207 Oswego City Library 120 E. Second Street Oswego,.
New York 13126
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's ENCLOSURE RE UEST FOR ADDITIONAL INFOL~fATION ECCS AND GETAB ANALYSES FOR NINE NILE POINT UNIT 1 Provide the axial power distribution used in the GETAB analyses.
2.'.>For the two most limiting (MCPR) transients as determined by the GETAB
- analyses, provide the maximum steamline pressure obtained and the time of limiting MCPR.
~ 3.
For the most limiting (MCPR) transient, provide time plots of the following parameters:
a) neutron flux b) surface heat flux c) steamline pressure d) vessel pressure e) actual skirt submersion (inches) f)
peak fuel center temperature g) feedwater flow h) vessel steam flow
~
i) turbine, steam flow j) core inlet flow k) recirculation flow 1) turbine pressure rise m) bypass valve flow n) relief valve flow o) safety valve flow
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For the most limiting (L~1CPR) transient, provide curves of neutron flux and surface heat flux versus core flow.
5.
The general description of the SAFE Code model used in the ECCS analysis is not consistent with the results provided as Figures A-la through A-lh.
Specifically, there is no change in the time of boiling transition for large and small breaks as was described.
Provide clarification of the SAFE Code model description.
6.
The information provided in support of partial loop operation. by your letter dated July 25, 1975 is not acceptable.
Our letter of June 18, 1975 provides guidelines in this matter. If partial loop operation is
- desired, provide adequate justification.
7.
Provide an explanation of the different values used for the void coefficient of reactivity as presented in Tables 5-1 and 6-1 of NED0-20772, "General Electric BNR Reload-5 Licensing Submittal for Nine i~file Point Nuclear Station, Unit 1".
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