ML18087A478

Application to Amend License DPR-75,consisting of one-time Deferral of Certain 18-month Surveillance Items Required by Tech Specs App A.Class III Amend Fee Encl

ML18087A478
Person / Time
Site:	Salem
Issue date:	09/17/1982
From:	Uderitz R Public Service Enterprise Group
To:	Varga S Office of Nuclear Reactor Regulation
References
LCR-82-18, NUDOCS 8209220286
Download: ML18087A478 (7)

Text

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Richard A. Uderitz Public Service Electric_ and Gas Company P.O. Box 236, Hancocks Bridge, NJ 08038 609 935-6010 Vice President -

Nuclear September 17, 1982 Director of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C.

20555 Attention: Mr. Steven A. Varga, Chief Operating Reactors Branch #1 Division of Licensing Gentlemen:

REGUEST FOR AMENDMENT TO FACILITY OPERATING LICENSE DPR-75 SALEM GENERATING STATION UNIT NO. 2 DOCKET NO. 50-311 In accordance with the Atomic Energy Act of 1954, as amended, and the regulations thereunder, we hereby transmit copies of our request for amendment and our analyses of the changes to Facility Operating License DPR-75 for Salem Generating Station, Unit No. 2.

This request consists of a one-time deferral of certain 18 month surveillance items required by Safety Technical Specifications, Appendix A.

A significant number of surveillance items listed in this request are sensor calibrations.

All sensors except Reactor Coolant Flow and First Stage Turbine Impulse Pressure detectors will be replaced in response to environmental qualification considerations during the first refueling outage for Unit No. 2.

This change involves a single safety issue and is deemed not to involve a significant safety hazard and is a Class III amendment as defined by 10 CFR 170.22.

A check in the amount of $4,000 is enclosed.

Enclosure

,--8209220286~820917 ---*-. - ---.

PDR ADOCK 050003'11 P

PDR

Ref. LCR 82-18 STATE OF NEW JERSEY)

) ss:

COUNTY OF SALEM COUNTY OF SALEM

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RICHARD A. UDERITZ, being duly sworn according to law disposes and says:

I am a Vice President of Public Service Electric and Gas Company, and as such, I find the matters set forth in our Request for Amendment dated September 17, 1982, are true to the best of my knowledge, information and belief.

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RICHARD h. UDERI~~~

Subscsribed and sworn_1.:o befo~e me this ' /7. day of ~ve~'

1982.

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j Not&ry Public of New Jersey My commission expires on ~

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PROPOSED LICENSE CHANGE SALEM UNIT NO. 2 DOCKET NO. 50-311 DESCRIPTION OF CHANGE LCR 82-18 A License Condition is required that provides a one-time deferral of 18 Month Technical Specification Surveillance items listed on the attached Table.

The listed surveillances, due to the number of items, the nature and location of the work required, and the time needed to accomplish each, would necessitate Mode 5, Cold Shutdown, approximately three months prior to the upcoming First Refueling outage for Salem No. 2.

The requested deferral will mandate that the required surveill-ances be completed prior to startup following the first cycle refueling presently scheduled for January 22, 1983.

REASON FOR CHANGE As a result of the numerous issues that arose from the TMI-2 accident, a long period of time elapsed between the issuance of the Salem No. 2 Low Power (5%) Testing License on 4-18-80 and the receipt of the Full Power License on 5-20-81. During this period, the unit was predominantly in Mode 5, Cold Shut-down.

The 18 Month surveillanr.es listed on the attached Table were performed after t~~.. -lnitiation of Low Power Test-ing and, being refueling-outage-type items, were not redone

.during the operationally inactive months that preceded the receipt of the Full Power License.

Since the beginning of commercial operation, no extended outage has occurred that would have facilitated the completion of the subject surveillances.

These circumstances combined to create a situation that is not expected to occur again.

Therefore, a one-time deferral is appropriate and has been suggested by the Nuclear Regulatory Comrnision as a reasonable method for obtaining temporary relief from the required Tech-nical Specifications surveillances *

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SAFETY EVALUATION The 18 month surveillances were based on an attempt to define a testing frequency to assure that instruments and equipment important to safety are periodically subjected to tests; inspec-tions and/or calibrations in a timely manner.while providing operational flexibility for scheduling and performance-consid-eratio~s during ~n normal 12 month fuel cycle.

Because of the protracted nature of the first fuel cycle, as discussed in the REASON FOR CHANGE *section above, the surveillance interval should be extended to provide the operational latitude that was intended as described in the Technical Specification Bases.

With the exception of the calibration of the Containment Sump Level (used as one method of leak detection) and the timing of 4KV circuit breakers, the items for which a deferral is re-quested are subjected to other, more frequent, surveillance tests that ensure their OPERABILITY during plant operation.

The Containment Sump Level Monitor is only one of several methods available for containment leak detection and the timing of 4KV Breakers has been historically satisfactory on Unit No. 1 in previous surveillance tests. Additionally, the instrument channels are redundant and are compared to corresponding channels (Channel Checks) at least once every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> so that any significant caiibration deficiency would be indentified.

Based on the considerations discussed above, and the fact that the longest deferral time required for any item listed constitutes only a 15.0% increase in the allowable surveillance interval for that item, it is concluded that this amendment does not involve a significant increase in the probability or consequences of any accident reviewed in the safety analysis report nor in the poss-ibility of an accident or malfunction of safety-important equip-ment of a different type than previously evaluated, and does not involve a significant decrease in safety margin as defined in the Technical Specifications Bases

• SALEM GENERATING STATION UNIT NO. 2 Mode 5 -

18 Months Surveillance due prior to the next refueling outage Operations Department DESCRIPTION Containment Spray Pump Auto Start Containment o A Isolation Test Containment o B Isolation Test Maintenance Department DESCRIPTION Containment Sump Level Monitoring System Channel Calibration 4kV Breaker Inspection and Timing:

2A4D 2B4D 2C4D 125VDC and 28VDC Eight Hour Battery Service Test:

2Al28VDC 2A228VDC 2Bl28VDC 2B228VDC 2Al25VDC 2Bl25VDC 2Cl25VDC SEC Sequencer Test and Output Relay Time Response Test:

2A SEC 2B SEC 2C SEC Hydrogen Recombiners Test

1. 21

1. 22 Diesel Generator Inspection 2A Diesel 2B Diesel 2C Diesel DUE DATE 1-07-83 1-12-83 1-12-83 DUE DATE 12-13-82 1-12-83 1-12-83 1-12-83 11-18-82 11-18-82 11-20-82 11-20-82 11-17-82 11-17-82 11-20-82 11-23-82 11-19-82 11-19-82 12-05-82 12-05-82 12-17-82 12-10-82 12-20~02

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SALEM GENERATING STATION UNIT NO. 2 Mode 5 -

18 Months Surveillance due prior to the next refueling outage Instrument and Control Department DESCRIPTION DUE DATE First Stage Turb. Impule Press -

CH I ChannelCalibr.

12-31-82 RC Flow -

Loop l -

CH I RC Flow -

Loop 1 -

CH II RC Flow -

Loop 1 -

CH III Sensor Calibr.

RC Flow -

Loop 2 -

CH I RC Flow -

Loop 2 -

CH II RC Flow -

Loop 2 -

CH III RC Flow -

Loop_3 -

CH I RC Flow -

Loop 3 -

CH II RC Flow -

Loop 3 -

CH III RC Flow -

Loop 4 -

CH I RC Flow -

Loop 4 -

CH II RC Flow -

Loop.4 -

CH III Pzr. Press. Prot. CH I Pzr. Press. Prot. CH II Pzr. Press. Prot. CH III Pzr. Level Prot.

CH I Pzr. Level Prot.

CH II Pzr. Level Prot.

CH III Pzr. Press Prot.

CH IV First Stage Turbine Impule Press -

CH I First.Stage Turbine Impule Press -

CH II

1. 21 S/G Stm Flow Prot. CH I

1. 21 S/G Stm Flow Prot. CH II

1. 21 S/G Level Prot.

CH IV

1. 21 S/G Level Prot.

CH III

1. 21 S/G Level Prot.

CH II

1. 22 S/G Stm Flow Prot. CH I

1. 22 S/G Stm Flow Prot. CH II

1. 22 S/G Level Prot.

CH IV

1. 22 S/G Level Prot.

CH III

1. 22 S/G Level Prot CH I

1. 23 S/G Stm Flow Prot. CH I

1. 23 S/G Stm Flow Prot. CH II

1. 24 S/G Level Prot.

CH IV

1. 23 S/G Level Prot.

CH IV

1. 23, S/G Level P~ot.

CH Irr

1. 23 S/G Level Prot. -

CH I

1. 24 S/G Stm Flow Prot. CH I

1. 24 S/G Stm Flow Prot. CH II

1. 24 S/G Level Prot.

CH IV

1. 24 S/G Level Prot.

CH III

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II II 1-16-83 1-13-83 1-13-83 1-20-83 1-14-83 1-20-83 1-16-83 1-14-83 1-17-83 1-17-83 1-14.-83 1-17-83 11-26-82 11-30-82 11-30-82 1-01-83 1-01-83 1-01-83 11-29-82 11-20-82

' 11-24-82 12-13-82 12-14-82 10-11-82 12-18-82.

12-17-82 12-05-82 12-05-82 10-21-82 12-28-82 12-22-82 12-07-82 11-14-82 12-20-82 10""'.26-82 11-13~82 11-01-82 12-06-'82 11-30-82 12-20-82 11-05-82

Instrument and Control Department (Continued)

DESCRIPTION

1. 24 S/G Level Prot.

CH II Containmen~ Press.

CH IV Containment Press.

CH III Containment Press.

CH II Containment Press.

CH I RC Hot Leg Press.

RC Hot Leg Press.

S/G #21 Wide Range Level S/G #22 Wide Range Level S/G #23 Wide Range Level S/G #24 Wide Range Level Turb. Aux. Speed Replace WR RTD Source Range Channel I Detector Calibration Source Range Channel II Detector Calibration SSPS External Input Test Hot Shutdown Panel Sensor Calibrations:

1. 21 S/G Level

1. 22 S/G Level

1. 23 S/G Level

1. 24 S/G Level

1. 21 S/G Press

'#22 S/G Press

1. 23 S/G Press

1. 24 S/G Press PZR Press.

PZR Level

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DUE DATE 11-05-82 11-23-82 11-27-82 11-25-82 11-27-82 12-03-82 12-04-82 12-30-82 12-31-82 12.;...28-82 12-14-82 12-25-82 1-01:--83 1-08-83 1-08-83 12-25-82 12-19-82 12-19-82 1-03-83 1-02-83 1-01-83 1-01-83 1-02-83 1-02-83 1-03-83 1-04-83