ML18092B379
| ML18092B379 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 12/18/1986 |
| From: | Corbin McNeil Public Service Enterprise Group |
| To: | Noonan V Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML18092B380 | List: |
| References | |
| GL-85-09, GL-85-9, NLR-N86174, NUDOCS 8612240245 | |
| Download: ML18092B379 (5) | |
Text
Public Service Electric and Gas Company Corbin A. McNeil!, Jr.
Vice President -
Public Service Electric and Gas Company P.O. Box 236, H ancocks Bridge, NJ 08038 609 339-4800 Nuclear December 18, 1986 NLR-N86174 Ref:
LCR 84-13 Off ice of Nuclear Reactor Regulation United States Nuclear Regulatory Commission 7920 Norfolk Avenue Bethesda, MD 20014 Attention:
Mr. Vincent s. Noonan, Director PWR Project Directorate #5 Division of PWR Licensing A Gentlemen:
REQUEST FOR AMENDMENT LICENSE CHANGE REQUEST SALEM GENERATING STATION UNIT NOS. 1 AND 2 FACILITY OPERATING LICENSES DPR-70 AND DPR-75 In accordance with the Atomic Energy Act of 1954, as amended and the regulations thereunder, Public Service Electric and Gas Company (PSE&G) hereby transmits copies of this request for amendment and analysis of the changes to Facility Operating License DPR-70 for Salem Generating Station Unit No. 1, and DPR-75 for Salem Generating Station Unit No. 2.
This request supplements LCR 84-13, originally submitted October 17, 1985.
The proposed changes are being submitted to achieve compliance with Generic Letter 85-09, regarding Technical Specification requirements for the Reactor Trip System.
The Action statements for modes 3, 4, and 5 with the reactor trip breakers closed will be revised to allow 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> for restoration to operability prior to requiring opening of the breakers to preclude control rod withdrawal.
In addition, a new Action statement is introduced to explicitly address both features of the reactor trip breakers.
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Mr. Vincent S. Noonan, Project Directorate #5 2
12-18-86 Pursuant to 10 CFR 50.9l(b) (1), a copy of this request for amendment has been sent to the State of New Jersey as indicated below.
This submittal includes three (3) signed originals and forty
( 4 0 ) copies
- C Mr. Donald C. Fischer Licensing Project Manager Mr. Thomas J. Kenny Senior Resident Inspector Sincerely, Mr. Samuel J. Collins, Chief Projects Branch No. 2, DPRP Region I Mr. David M. Scott, Acting Chief Bureau of Radiation Protection Department of Environmental Protection 380 Scotch Road Trenton, NJ 08628 Honorable Charles H. Oberly, III Attorney General of the State of Delaware Department of Justice 820 North French Street Wilminqton, DE 19801
Ref:
LCR 84-13 STATE OF NEW JERSEY COUNTY OF SALEM
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)
SS.
Corbin A. McNeil!, Jr., being duly sworn according to law deposes and says:
I am Vice President of Public Service Electric and Gas Company, and as such, I find the matters set forth in our letter dated December 18, 1986
, concerning Facility Operating Licenses DPR-70 and DPR-75, is true to the best of my knowledge, information and belief.
Subscrib~ and Sworn4to ~Jfore this /ff' day of P~
me 1986
~~
'Nf 1PA.l bl f N J
LARAINE Y. BEARD o ary {/
lC o ew ersey NotaryPublicofNewJersey My Commission Expires May 1, h'9l My Commission expires on -~~~~~~~~~~~~~~~~~
PROPOSED LICENS£ CHANGE SALEM GENERATING STATION UNIT NOS. 1 AND 2 DOCKET NOS. 50-272 AND 50-311 REACTOR TRIP BREAKERS LIMITING CONDITION FOR OPERATION Description of Change LCR 84-13 Page 1 of 2 Change Technical Specifications Table 3.3-l*for Salem Unit Nos. 1 and 2 to agree with the attached revised pages.
Reason for Change This change will supplement LCR 84-13, submitted 10-17-84, to comply with the guidance of Generic Letter 85-09 regarding Technical Specification requirements for reactor trip breakers.
It will revise the ACTION statements for the reactor trip breakers and automatic trip logic during Modes 3, 4 and 5 with the breakers in closed position and _the capability for control rod withdrawal.
The proposed ACTION statement would require restoration to OPERABLE status within 4R hours or opening of the trip breakers within the next hour.
Currently, th~ ACTION statement requires that HOT STANDBY be achieved within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
This is not appropriate for modes 3, 4 and 5.
Opening the trip breakers while in these modes will provide an added degree of safety to preclude inadvertent control rod withdrawal.
The proposed change will also revise the limiting conditions of operation during modes 1 and 2.
If either of the diverse trip features (undervoltage or shunt trip attachment) are inoperable, they will either be restored to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or HOT STANDBY will be achieved within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
This will ensure operability of both constituents of the reactor trip breaker.
This is consistent with the modifications resulting from the requirements of Generic Letter 83-28, "Required Actions Based on Generic implic~tions of Salem ATWS Events."
Significant Hazards Consideration A.
The probability of occurrence or the consequences of an accident or malfunction or equipment important to safety previously evaluated in the safety analysis report will not be significantly increased.
These changes are proposed in order to achieve consistency with the Westinghouse generic design rnodif ications to the reactor trip breakers.
These modifications and the associated proposed Technical Specifications increase the reliability of the breakers, thereby reducing the probability of malfunction and the consequences of an ace ident.
LCR 84-13 Page 2 of 2 B.
The pos~ibility of an accident or malfunction of a different type than any evaluated previously in the safety analysis report will not be created.
Since the reactor trip breaker modifications and these proposed changes were initiated to meet staff requirements for improving the breakers, no new type of accident or malfunction will be created.
C.
The margin of safety as defined in the basis for any Technical Specification is not reduced.
This proposed change will provide an additional degree of safety in the event that the reactor trip breakers become INOPERABLE during modes 3, 4, or 5 by requiring the trip breakers to be opened.
Also, this change explicitly addresses both diverse components of the breakers to achieve consistency with Westinghouse Standard Technical Specifications and the guidance of Generic Letter 85-09.
Therefore, it will not reduce the margin of safety for any Technical Specification.
Based on the above evaluation, we have determined that the proposed change does not involve a significant hazards consideration.