ML17054A425
| ML17054A425 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 01/30/1984 |
| From: | Miraglia F Office of Nuclear Reactor Regulation |
| To: | Novak T Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8402080439 | |
| Download: ML17054A425 (8) | |
Text
Docket No. 50-410 MEMORANDUM FOR:
Thomas M. Novak, Assistant Director for Licensing Division of Licensing FROM:
SUBJECT'rank J. Miraglia, Assistant Director for Safety Assessment Division of Licensing SAFETY EVALUATION REPORT - NINE MILE POINT UNIT 2 Enclosed are the inputs for Section 13.6, "Physical Security" and Section 16.0, "Technical Specifications," for the Nine Mile Point Unit 2 Safety Evaluation Report.
If you have any questions regarding the SER inputs, contact Mr. Eugene kl. McPeek (x24782) regarding Section 13.6 and Mr. Donald R. Hoffman (x28515) regarding Section 16.0.
Enclosures:
As stated cc:
M. Haughey "OrXgiaal signed, by 7razQr. Z. Miraglia Frank J. Miraglia, Assistant Director for Safety Assessment Division of Licensing DISTRIBUTION:
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Docket No. 50-410
%V UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 JAN 30 884 MEMORANDUM FOR:
Thomas M. Novak, Assistant Director for Licensing Division of Licensing FROM:
~ ~ -
SUBJECT:
Frank J. Miraglia, Assistant Director for Safety Assessment Division of Licensing SAFETY EVALUATION REPORT - NINE MILE POINT UNIT 2 Enclosed are the inputs for Section 13.6, "Physical Security" and Section 16.0, "Technical SpecificatioJIs," for the Nine Mile Point Unit 2 Safety Evaluation Report.
If you have any questions regarding the SER inputs, contact Mir. Eugene t0.
McPeek (x24782) regardina Section 13.6 and Mr. Donald R. Hoffman.(x28515) regarding Section 16.0.
Enclosures:
As stated cc:
M. Haughey Frank J.
aglia, Assistant Director for Safety Assessment Division of Licensing
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50-410 LOSURE NINE NIlE POINT NUCLEAR STATIONS UNIT 2 DRAFT SAFETY EVALUATION REPORT INPUT SECTION 13.6 The appli cant has submitted security plans entit led "Wine t'ai Le Point Nuclear Station Physical Secur ity Plan"~ "Nine Nile Point Nuclear Station Safeguards Contingency Plan"~
and "Nine Ni Le Point Nuclear Station Security Training and Qualification PLan" ~ for protection against radiological sabotage.
The training and qualification plan has been reviewed in accordance with Section 13.6 "Physical Security" of the July 1981 edition of the "Standard Review PLan for the Review of Safety Analysis Reports for Nuclear Power PLants" ~
(SRP~
The Security PLan and the Safeguar ds Contingency Plan are currently under staff review in accordance with the above.
As a result of our evaluation~
the training and qualification plan has been approved.
Certain portions of the Security PLan and the Contingency PLan have been identified as requiring, additionaL information to satisfy the requirements of 10 CFR 73.55.
The applicant is expected to make commitments acceptable to the staff~ which when formaLLy incorporated into these planning documents~
wiLL bring them into comp liance with the Commission's regu lations contained in 10 CFR Parts 50 and 73.
The applicant's security plans are being protected fron unauthorized discLosure in accordance with Section 73.21 of 10 CFR Part 73.
ly
50-410 ENCLOSURE 16 TECHNICAL SPECIFICATIONS The Technical Specifications iri a license define certain features, characteris-
- tics, and conditions governing operation of a facility that cannot be changed without prior approval of the NRC staff.
The finally approved Technical Speci-fications will be made a part of the operating license.
Included will be sec-tions covering definitions, safety limits, limiting safety system settings, limiting conditions for operations, surveillance requirements, design features, and administrative controls.
Staff preparation of the Technical Specifications for the Nine Mile Point facility will begin approximately 12 to 18 months prior to the expected fuel load date using the then current version of the "Standard Technical Specifications for General Electric Boiling Water Reactors" (NUREG-0123).
On the basis of its review to date, the NRC staff concludes that normal plant operation within the limits of the Technical Specifications will not result in offsite exposure in excess of the 10 CFR 20 limits.
Furthermore, the limiting conditions for operation and the surveillance requirements will ensure that necessary engineered safety features will be available in the event of malfunctions within the facility.
During its review of the Nine Nile Point application, the NRC staff identified certain issues that must be included in the Technical Specifications as a condition of NRC staff acceptance.
These issues are identified in various sections of this SER.
Most of the issues that the NRC staff has identified as being required to be included in the Nine Mile Point Technical Specifications are already addressed in NUREG-0123.
Those issues that are not included in NUREG-0123 will be added to the Technical Specifications being prepared for the Nine Mile Point facility.
Nine M:1 e Point
- SEP, I6-1
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