ML20199J619

Safety Evaluation Supporting 851216 Proposed Mods to Tables 4.3-1 & 4.3-7 of Recovery Operations Plan.Replacement Pages Encl

ML20199J619
Person / Time
Site:	Three Mile Island
Issue date:	06/26/1986
From:	Office of Nuclear Reactor Regulation
To:
Shared Package
ML20199J610	List: ML20199J603 ML20199J619
References
NUDOCS 8607080383
Download: ML20199J619 (7)

Text

4 SAFETY EVALUATION B.Y-Tile OFFICE OF NUCLEAR REACTOR REGULATION FOR RECOVERY OPERATIONS PLAN CHANGE REQUEST 35 INTRODUCTION By letter dated December 16, 1985, the licensee requested approval for modifications to the T!!I-2 Recovery Operations Plan (ROP). This request was supplemented in a discussion with the licensee's staff held on Iiarch 27, 1986.

These changes involve revisions to Tables 4.3-1 and 4.3-7 of the R0P, as discussed below.

EVALUATI0ti The licensee proposes to make several changes to Table 4.3-1, to correct administrative errors arising from NRC R0P Change flo. 31, issued October 21, 19P;5 (GPUllC R0P Change Request flo. 29). In ROP Change No. 31, the neutron monitoring instrumentation surveillance requirements were listed solely in Table 4.3-1; previously, some requirements were also specified in Table 4.3-7.

Consolidating the requirements resulted in some administrative errors,to Table 4.3-1. The current request corrects these errors by making the following changes to Table 4.3-1:

1) The addition of a note which states " Intermediate and Source Range and Rate is not required at Cabinet 217."

2) Changing the frequency of channel checks frcm once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> to monthly for Cabinet 217, with a note to that effect. The channel check frequency will remain once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for the control room readout channels.

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ll 2 The first change is necessary because prior to R0P Change flo. 31. Table 4.3-7 specified the surveillance reqTirements for the Intermediate anyource Range Neutron Flux level monitors, including the readout locations in the control i <

room and at Cabinet 217. Table 4.3-1 also specified surveillance requirements

! i for the neutron flux level monitors, and, additionally, the neutron flux rate

, monitors; however, this table did not identify readout locations. In R0P Change No. 31, Table 4.3-1 was revised to include the neutron flux level monitor readout locations previously listed in Table 4.3-7, however, the l neutron flux rate monitors were incorrectly identified as having readout capability at Cabinet 217. This oversight will be corrected by the proposed change.

The second correction to Table 4.3-1 is related to the first. Prior to R0P Change Ho. 31, Table 4.3-7 required monthly channel checks for the neutron flux level monitors at the control room and Cabinet 217 readout locations.

Table 4.3-1 required channel checks every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for the neutron flux level and rate monitors at the control room readout locations only. The proposed I change will restore the monthly channel check frequency for the neutron flux level monitoring instrumentation in Cabinet 217. This frequency is consistent with the original intent of the requirement and will minimize the wear and tear on the equipment in Cabinet 217. The channel check frequency will remain at once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for the neutron monitoring instrumentation control room J

readout locations. These two changes are administrative in nature and will correct discrepancies found in an earlier revision to the R0P, therefore the staff finds them acceptable.

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The licensee also proposes to modify Table 4.3-7 by adding an alternate readout location for Reactor Building Water Level indication. The licensee has installed this alternate level indication, consisting of a probe and level indicating transmitter with readout in the Hot Instrument Shop. The proposed change will improve Reactor Building Water Level monitoring reliability by providing an additional capability for surveillance, thus allowing greater operational flexibility.

The staff concludes that the proposed changes to the R0P do not pose a significant risk to the health and safety of the public and that the proposed changes are within the scope of activities and events analyzed in the PEIS. We therefore approve the proposed changes to the THI-2 Recovery Operations Plan as discussed herein. Our approval of GPU R0P Change Request flo. 35 is flRC R0P Change Approval No. 32.

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Enclosure FACILITY OPERATING LICENSE N0. DPR-73 DOCKET f!0. 50-320 Replace the following pages of the Ti1I-2 Recovery Operations Plan with the enclosed pages as indicated:

4.3-2 .

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TABLE 4.3-1 f>3 E5 NEUTRON MONITORING INSTRUMENTATION

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CHANNEL MINIMUM CHANNEL CHANNEL FUNCTIONAL TOTAL N0. CHANNELS CHANNELS READ OUT FUNCTIONAL UNIT CHECK CALIBRATION TEST OF CHANNELS TO TRIP OPERABLE LOCATIONS

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1. Intermediate' Range, Neutron S/M(4) R(1) M 2 0 1 Cab 217 +(2&3)

Flux Rate Control Room

2. Source Range, Neutron Flux S/M(4) R(1) M 2 0 2 Cab 217 +(2&3) f=

ja and Rate Control Room m

NOTES

1) Neutron detectors and all channel components located inside containment may be excluded from CHANNEL CALI-BRATION.

2) Only one readout required at Cabinet 217.

3) Intermediate and Source Range is not required at Cabinet 217.

4) Monthly channel check applies only to Cabinet 217.

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- jl TABLE 4.3-7 m

2 ESSENTIAL PARAMETERS MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS 3:

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- MINIMUM l gj CHANNEL CHANNEL (1) READOUT OPERABLE INSTRUMENT CHECK CALIBRATION LOCATION (S) CHANNELS

- ~Si El 1. Reactor Building Pressure S R Control Room 2 SA Control Room (2) 2(2)

2. Reactor Vessel Water Level S/W(2)

3. Incore Thermocouples/RCS S R Control Room or 2(3)

Temperature Detectors Cable Room

4. Reactor Building Water Level NA SA Control Bldg. 1

• - Area West or Hot i) Instrument Shop "o

5. Borated Water Storage Tank S R Control Room 1 i Level

6. Steam Generator Level NA NA NA 1/ Generator

7. Spent Fuel Storage Pool S/W(2) SA Control Room (2) 2(2)

"A" Water Level or Fuel Handling

Bldg.

c. so 8. Fuel Transfer Canal S/W(2) SA Control Room 2(2) g 53 (deep end) Water Level or Reactor Bldg.

mn g( [ (See following page for notes)

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TMI-2 SERVICE LIST Dr. Thomes Murley Willis 'Staly. Site Matager Regional Administrator. Region i U.S. Department of inergy U.S. nuclear Regulatory Comission P.O. Boa 88 631 Park Avenue Middletown. PA 17057-0311 L King of Prussia. PA 19406 (

David J. McGoff John F. Wolfe. Esq.. Chairman. Division of Three Mile Island Programs Administrative Judge NC-23 3409 Shepherd St. U.S. Department of Energy Chevy Chase. MD. 20015 Washington. D.C. 20545 Dr. Oscar H. Paris William tochstet Administrative Judge 104 Davey Laboratory AtomlC Safety and Licensing Pennsylvania State University University Park. PA 16802.

Board Panel U.S. Nuclear Regulatory Comission Washington D.C. 20555 Randy Myers. Editorial The Pa triot

• Administrative Dr. Frederick H.Judge Shon

• 812 Market 5t.

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[secutive vice Prestdent Thomas M. Gerusky. Director General Public Uttlities NvClear Corp.

100 gr.terpace Part.ay Bureau of Radiation Protection Persip;,any. NJ 07054 Department of Environraental Resources P.O. 6am 2063 rarrisburg. PA 17120 Ad Crable

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