ML18087A671
| ML18087A671 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 01/27/1983 |
| From: | Liden E Public Service Enterprise Group |
| To: | Varga S Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML18087A672 | List: |
| References | |
| LCR-82-16, NUDOCS 8302180497 | |
| Download: ML18087A671 (4) | |
Text
PS~G Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Nuclear Department January 27, 1983 Director of Nuclear Reactor Regulation
- u. s. Nuclear Regulatory Commission 7920 Norfolk Avenue Bethesda, Maryland 20014 Attention:
Mr. Steven A. Varga, Chief Operating Reactors Branch #1 Division of Licensing
Dear Mr. Varga:
REQUEST FOR ADMENDMENT TO FACILITY OPERATING LICENSES DPR-70 AND DPR-75 SALEM GENERATING STATION UNIT NOS. 1 AND 2 DOCKET NOS. 50-272 AND 50-311 Ref. LCR 82-16 In accordance with the Atomic Energy Act of 1954, as amended, and the regulations thereunder, we hereby transmit copies of our request for amendment LCR 82-16 and our 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.
These changes will establish system operability requirements for the. transfer functions of the ECCS Semiautomatic Switchover from Safety Injection to Recirculation during a LOCA.
Since the installation of the actual plant modifications are sched-uled to be accomplished during the upcoming refueling outage on Unit No. 2, and at the next refueling outage on Unit No. 1, we request that implementation of the Technical Specifications requirements proposed in this change be keyed to the completion of the plant modifications on a Unit basis, such that Unit 2 A OJ Technical Specifications are implemented following the first 0
-~efueling outage, ~nd Unit ~Technical.Specifications are Sf
'1.mplemented following_ the fifth refueling outage.
I 'I 0
- a3o2"ieo497 030127 PDR ADOCK 05000272
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p PDR Wf c 6c I';;
cj yyoa.oo The Energy People 95-21 68 (80 M) 11-82
Mr. Steven A. Varga, Chief u.s. Nuclear Regulatory Commission 1/27/83 These changes involve a single safety issue and are therefore determined to be a Class III and a Class I amendment as defined by 10CFR 170.22.
A check in the amount of $4,400 is enclosed.
This submittal includes three (3) signed originals and forty (40) copies.
Enclosures very truly yours, Manager -
Nuclear Licensing and Regulation
STATE OF NEW JERSEY SS.
COUNTY OF SALEM COUNTY OF SALEM RICHARD A. UDERITZ, being duly sworn according to law deposes and says:
I am a vice President of Public Service Electric and Gas Company, and as such, I find the m.a t t~_;i::-s set forth in our Request for Amendment LCR 82-16 d.a,te'd Janua~y 27, 1983, are true to the best of my knowledge, information and *belief.
Subscribed and sworn to before me this 3l<St. day of Ja.nuar~
, 1983
~J~~rsey RUDOLPH L. von FISCHER JR.
Notary Public of New Jersey My Commission expires on My Commission Expires Sept. 10, 1986
_.:i.,
DESCRIPTION OF CHANGE Add the semiautomatic transfer functions to appropriate instru-ment tables; Table 3.3-3 ESF ACTUATION SYSTEM INSTRUMENTATION, Table 3.3-4 ESFAS INSTRUMENT TRIP SETPOINTS, Table 3.3-5 ESFAS RESPONSE TIMES, Table 4.3-2 ESFAS INSTRUMENTATION SURVEILLANCE REQUIREMENTS, Table 3.3-lla and b, ACCIDENT MONITORING INSTRU-MENTS, and delete the SJ44 valves from section 4.5.2 of ECCS Surveillance Requirements.
REASON FOR CHANGE The proposed changes will establish system operability require-ments consistent with those of protection system equipment.
SAFETY EVALUATION This change provides a method to automatically transfer RHR pump suction from the RWST to the Containment Sump in the event of concurrent Safety Injection and RWST low level.
A descrip-tion of the associated plant modifications is provided in the attached design description.
The automation of certain steps in the LOCA switchover procedure will save both time and RWST volume thus increasing the safety margin of all ECCS pump suctions and conserving RWST volume.
The automation of a number of steps in the switchover sequence eliminates the remote manual manipulation of six ECCS valves and the stopping and restarting of the RHR pumps.
This feature of the design eliminates the possibility of operator error for those steps which are being automated in the switchover sequence.
The failure of one logic train of semiautomatic switchover to recirculation to actuate does not cause the total loss of one ECCS train.
The equipment remains available and operator action on a component level will effect a manual transfer to recirculation for the affected equipment.
It is therefore concluded that implementation of this change does not involve an unreviewed safety question and poses no undue risk to the health and safety of operating personnel or the general public.
BASIS FOR FEE CLASSIFICATION The NRC has clearly identified the requirement for semiauto-matic switchover in the Salem SER (Supplement 4, Section 6.3.3).
This change is deemed not to involve a significant hazards consideration and is therefore determined to be a Class III amendment, and a Class I amendment for the second unit.