ML20092A355

Application for Amend to License DPR-50,consisting of Rev 1 to Tech Spec Change Request 114,revising Accident Monitoring Instruments & post-accident Monitoring Instrumentation Tables

ML20092A355
Person / Time
Site:	Three Mile Island
Issue date:	06/13/1984
From:	Hukill H GENERAL PUBLIC UTILITIES CORP.
To:
Shared Package
ML20092A354	List: ML20092A348 ML20092A355 ML20092A369
References
NUDOCS 8406190170
Download: ML20092A355 (3)

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METROPOLITAN EDISON COMPAh7 JERSEY CENTRAL POWER & LIGHT COMPAh7 AND PENNSYLVANIA ELECTRIC COMPAhT THREE MILE ISLAND NUCLEAR STATION, UNIT 1 Operating License No. DPR-50 Docket No. 50-289 .;

Technical Specification Change Request No.114 Ibv.1  !'

- This Technical Specification Change Request is submitted in support of Licensee's request to change Appendix A tu Operating License No.

DPR-50 for Three Mile Island Nuclear Station, Unit 1. As a part of this request, proposed replacement pages for Appendix A are also included.

GPU NUCLEAR CORPORATION By Director, TMI-l l .

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Sworn and subscribed i

to before me this. h day of Ch-a > , 1984 A. . w Au ,

NotaVy Public' 4 DARLA JfAN BERiiV. NOTARY PUBLIC M100LETOWN BORO. DAUPHIN COUNTY uv c0emssl0E EXPIRES JUM 17.1985 Sunbet F- * .__ Amocation nf NMans 8406190170 840613 DR ADOCK 05000289 <

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TECHNICAL SPECIFICAT1CW CHARGE REQUEST (TSCR) NO. 114, REV. 1.

The Licensee requests that! the attached changed pages replace pages vi, 3-40a, 3-40b, 4-1. and 4-Sa of the Technical Specifications as amended through Amendment 9S. Changes made to the attached enanged pages should oe incorporated as necessary into tne Technical Specifications to reflect amendments issued subsequent to Amendment 95. These revised pages stpercede TSCR 114, Rev. O.

REASON FOR TSCR 114, REV. 1 This revision is provided to resolve NRC review comments on TSCR 114, Rev.

O. The revisions make this request more consistent witn the NRC model Tech Specs. (GL 83-37).

SAFETY EVALUATION l The Safety Evaluation for TSCR 114 Rev. O remains valid and applicable.

In addition, the following supporting information is provided.

1. The applicability form 7.5.5.2 is appropriate and does not specify HOT SHUTDOWN t,., ce consistent with Action 8 of taale 3.5-3 to proceed to a condit.% where tne equipment is not required to be operaole. >

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2. Table 3.5-3 does not include alarm setpoints for radiation monitors, since they may be subject to repeated change due to operating experience, detector replacement, and maintenance.

Operability of the alarms is covered by the definition of OPERABLE per TSCR 139, Rev. 1. The ranges for tne monitors are provided in the Restart Report and FSAR.

3. Action A is appropriate since the emergency planning procedures provide backup means for projecting releases and does assessment using other available plant parameters in tne event one of tne '

high range mc".itors is unavailaole. These procedures are in place ano available for use at all times.

Reporting of monitor unavailability within 30 days was selected i:o oe consistent witn 10 CFR 50.73.

4. Action 8 time frames are appropriate since the below listed _

alternate single channel control grade means are available as backup monitors:

a. Containment pressure 0-100 psi.

b. Containment water level 0-10 ft.

- c. Containment Hydrogen via air samples (II.B.3). In addition, greater than 7 days is required before Hydrogen reaches 4% following a LOCA.

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'J 5. The Surveillance checks specified in taole 4.1-4 were selected to be consistent with the weekly checks for the normal range radiation monitors. This is appropriate in light of the likelDiood of U1eir use compared to Ulat of tie normal range monitors.

6. Surveillance frequencies for the Containment Hydrogen monitor are appropriate since the monthly test includes a calibration check at 1% and 10% Hydrogen using calibration gas. The refueling calibration uses 1%, 4% and 10% calibration gasses.

The weekly check is consistent with action B requirement of table 3.5-3.

NO SIGNIFICANT HAZARDS CONSIDERATION This TSCR provides additional TS to assure ble operability of equipment installed to monitor variables important to post accident plant status assessment. This change represents an increase in requirements.

Therefore this TSCR would not:

1. Alter probability of any accident previously evaluated and may be able to reduce the consequences of an accident.

2. Create U1e possibility of a different kind of accident, since the TSCR is administrative only.

3. Involve a reduction in the margin of safety, since it represents an increase in requirements.

IMPLEMENTATION In order to finalize procedures to reflect revisions to tnis TSCR, an implementation period of 45 days is needed. The amendment approving this TSCR should be effective 45 days after approval by NRC.

A!ENDtENT CLASSIFICATION (10 CFR 170.22)

This is a Class II amendment since it is administrative in nature. A l check for $1,200.00 is attached. '

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