ML20212D935

From kanterella
Jump to navigation Jump to search

Forwards Revised Pages to 860807 Rev 1 to License Change Application 130,amending License NPF-1 to Change Tech Specs Re Plant Review Board Review of Procedures,Per 861216 Telcon
ML20212D935
Person / Time
Site: Trojan File:Portland General Electric icon.png
Issue date: 12/31/1986
From: Lindblad W
PORTLAND GENERAL ELECTRIC CO.
To: Varga S
Office of Nuclear Reactor Regulation
Shared Package
ML20212D940 List:
References
TAC-60020, NUDOCS 8701050167
Download: ML20212D935 (2)


Text

-___ _ --

PONTLAND GENEHAL ELECTHIC COMI%NY 121 S. W. S A LM O N STREET WILLIAM J. LINDBLAD PoRTLAN o. O R EGO N 97204 (503)226-8875 December 31, 1986

)

Trojan Nuclear Plant Docket 50-344 License NPF-1 l

Director of Nuclear Reactor Regulation ATTN: Mr. Steven A. Varga Director, PWR-A Project Directorate No. 3 U.S. Nuclear Regulatory Commission Washington DC 20555

Dear Sir:

License Change Application 130 Revision 1 Plant Review Board Review of Procedures Pursuant to a telephone conversation with members of your staff on December 16, 1986, attached are two revised pages for insertion into Revision 1 of LCA 130, dated August 7, 1986. These pages correct an error in the Significant Hazards Consideration that was overlooked when Revision 1 to LCA 130 was submitted and a typographical error in Technical Specification 6.5.1.6(f).

Sincerely,

/ D.

Attachment c: Mr. David Kish, Acting Director State of Oregon Department of Energy 8701050167 861231 g PDR ADOCK 05000344 P PDR hp 3

LCA 130, Revision 2 Page 8 of 8 which states in Section 13.2, "The Plant Review Board is advisory to the Plant Superintendent and will review all proposed tests, changes in operat~

ing procedures, and design modifications." It is not clear if the SER is referring only to the Operating Instructions (OIs), the General Operating Instructions (GOIs) Off-Normal Instructions (ONIs), and Emergency Instructions (EIs) or the entire Plant Operating Manual (POM). In any case, by reviewing the Technical Specifications issued to the plants recently obtaining an Operating License, it is obvious that the NRC position has changed. The Administrative Controls for San Onofre Units 2 and 3, Catawba, and McGuire Nuclear Plants are almost identical to those proposed changes in this LCA, requiring procedures and procedure changes to be reviewed and approved by any one of several plant departmental managers or tLe Station Manager and not the Onsite Review Committee. In addition, the Technical Specification Administrative Controls for Palo Verde, Grand Gulf, Byron, Callaway, Susquehanna, and LaSalle are somewhat similar in that the Onsite Review Committee does not have to review all of the safety-related procedures and procedure changes but only certain ones, or a separate group of individuals is established to perform the necessary reviews. Management review is adequate especially since the TNOB reviews the safety evaluations for procedure changes and the Nuclear Quality Assurance Department performs periodic audits of this activity. It is concluded that this LCA would nat have an effect on nuclear safety as a result of any other licensing document, commitment, or criteria.

CAZ/kal 5537k.1286 Q