ML20133C650

Proposed Tech Spec Change Request 141,revising Table 4.1.1 to Delete Requirement of Daily Channel Check for Low Reactor Water Level & lo-lo Water Level Instrument Channels

ML20133C650
Person / Time
Site:	Oyster Creek
Issue date:	09/30/1985
From:	GENERAL PUBLIC UTILITIES CORP.
To:
Shared Package
ML20133C644	List: ML20133C642 ML20133C650
References
NUDOCS 8510070476
Download: ML20133C650 (4)

Text

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i 0YSTER CREEK NUCLEAR GENERATING STATION '

PROVISIONAL OPERATING LICEriSE NO. DPR-lb DOCKET No. 50-219 TECHtdICAL SPECIFICATION CHANGE REQUEST r10. 141 Applicant hereoy requests the Commission to change Appendix A to tne above captioned license as follows:

1. Sections to be changed:

Taole 4.1.1 on page 4.1-o

2. Extent of Changes:

Delete the requirement of a daily enacnel cneck for the following instrument cnannels:

1) Low Reactor Water Level

2) Low-Low Water Level

3. Changes Requested:

Revise page 4.1-5 (Table 4.1.1) ,

4. Discussion:

Tecnnical Specification Cnange Request No.141 reflects tne replacement of two sets of non-environmentally qualified indicating pressure switches with two sets of environmentally qualified non-indicating switenes. Tne new environmentally qualified switches do not nave indicating gauges, tnerefore, tne requirement of a daily channel cnecK cannot be performed.

8510070476 850930 PDR ADDCK 05000219 p PM

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OYSTER CREEK NUCLEAR GENERATING STATION PROVISIONAL OPERATING LICENSE NO. DPR-16 00CKET NO. 50-219 TECHNICAL SPECIFICATION CHANGE REQUEST NO. 141 Pursuant to 10CFR 50.91 an analysis concerning significant hazards considerations is provided below:

1. Sections to be changed:

Table 4.1.1

2. Extent of changes:

Delete the requirement of a daily channel check for the following instrument channels:

1) Low Reactor Water Level

2) Low-Low Water Level

3. Discussion:

The Oyster Creek Technical Specifications, Table 4.1.1, titled Minimum Check, Calibration and Test Frequency for Protective Instrumentation, requires that a daily channel check be pdrformed on the Low and Low-Low-Reactor Water Level instrument channels. These two parameters (8 switches total) are currently equipped with indicating gauges.

However, during our 10(M) (maintenance) outage, these two sets of non-environmentally qualified switches are scheduled to be replaced with environmentally qualified non-indicating switches that perform the protective safety function.

These new switches are similar to instruments in Table 4.1.1 which do not require daily channel check such as: High Reactor Pressure and Low-Low-Low Water Level.

The daily channel check presently conducted does not actually " check" the safety function. Verifying the operability of the switch can only be done by causing the switch to change condition wnich is done monthly.

The safety function will be adequately tested by the Technical Specification calibration and test requirements listed in Table 4.1.1.

Examples of amendments that are considered not likely to involve significant hazards considerations were provided in the Federal Register on April 6, 1983 (48 FR 14870). Technical Specification Change Request No.141 meets the provisions of example (vii) which is "a change to make a license conform to cnanges in the regulations, where the license change results in a very minfor change to facility operations clearly in keeping with the regulations". A copy of the modified page is provided.

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4. Determination:

We nave determined that tne suuJect change request involves no significant hazards in operating tne Oyster Creek Nuclear Generating Station in accordance wito with Tecnnical Specification. Cuange Request No.141 would not:

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1. Involve a significant increase in ene probacility or tne consequence of an accident previously evaluated; or

2. Create tne possioility of a new or different Kind of accident from any previously evaluated; or

3. Involve a significant reduction in a margin of safety.

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8e T Abt E 4.1.1 MINIMMM enastE. CALImaATISM AND TEST FREGUENCY FOR PRSTECTIVE IIRSTRAIIGENTATIARI i

lastrumant Chanaal Check Calibrate Isai Remarka (Amatias ta Test and Callbratien) l 1. Mieh Reacter Pressure NA 1/3 me. Note 1 By aprilsatten of test pressure i

j 2. Nlsh Bryeeell Pressure (Scram) N A 1/3 me. Note 1 By appilsation of test pressure

] 3. Lees Reacter Meter Level NA 1/3 me. Note 1 By appilcation of test pressure

4. Low-Lees Meter Level NA 1/3 me. Note 1 By app!Ication of test pressure i

l' 5. Nish Meter Level in Scram NA 1/3 me. Note 1 By varying level la multch columns Bischeroe volume

6. Lees-Low-Lew Water Level NA 1/3 me. Note 1 By appilcation of test pressure

7. Nish Flow in Main Steamling 1/d 1/3 me. Note 1 By appilcation of test pressure

8. Lew Pressure in Mein NA 1/3 me. Note 1 By appilcatlen of test pressure Steenline

9. Nish Drvuell Pressure 1/d 1/3 me. Note 1 By appilcation of test pressure I

(Cere Coellas)

10. Mein Steen Isolatten Velve NA NA 1/3 me. By exercising valve (Scram)

11. APRM Level NA 1/3d NA . Sutput adjustment using operational type j heat belance during power operation

! APRM Scram Trips Note 2 1/uk 1/sek using built-in calibration espulpment during peeser operetlen

12. APRM Red Blocks Mete 2 1/3 me 1/me Upscale seul desenecale

) 13. a. Nish Radiation in Main 1/s 1/3 se 1/eek Using beslit-in calibration seculpment j Steamline during penser operetten

b. Sensers for 13(a) NA Each refuel NA using external r'adiation source ins eutage 4

i IIOTE 1: Initially once/so, thereafter according to Fig. 4.1.1, with an interval not less than one month

• 1 nor more than three months,

! t;sto 2: 1.t least daily iluring reactor pwer operation, the seactor neutron flux peaking factor shall be estimatea y

} and the f1w-refeicaced APR;4 scru and rad block betti.sgs shall be adjusted, if necessary, as specified in Sect ion 2.3, Spec!ficationn (1) (a) .md (2) (a).

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