ML20153E847

Safety Evaluation Approving Request for Mod of Recovery Operations Plan Table 4.3.3

ML20153E847
Person / Time
Site:	Three Mile Island
Issue date:	08/30/1988
From:	Office of Nuclear Reactor Regulation
To:
Shared Package
ML20153E837	List: ML20153E833 ML20153E847
References
NUDOCS 8809070035
Download: ML20153E847 (4)

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+ UNITED STATES

! 't, NUCLEAR REGULATORY COMMISSION

$ WASHINGTON, D. C. 20555

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SAFETY EVALUATION BY THE_0FFICE OF NU_C_ LEAR _R_EACTOR REGULATION glATINGT0FACILITYOPERATINGLICENSENO.DPR-73 GPU NUCLEAR CORPORATION THREE_ MILE I_SLAND NUCLEAR STATION, UNIT NO._2 DOCKET NO. 50-320 INTRODUCTION -

The Waste Handling and Packaging Facility (WHPF) is a building which houses equipment to process and package dry active waste (DAW) and contaminated tools and equipment. The WHPF is limited to containing not more than 15 curies of radioactivity at any one time. The WHPF ventilation system r.aintafils the building at a negative pressure with respect to the environment, provides for air flow from low contamination areas to higher contamination areas, and provides a filtered, monitored, release point. The WHPF monitor samples and analyzes the effluent air downstream of the filter bank.

EVALUATION The AMS-3 current monitor installed in the WHPF is a fixed filter beta, gama monitor. While designed as a local area monitor, it functioned adequately as an effluent monitor in this particular application. The licensee has proposed replacing the monitor with a particulate, iodine, noble gas (PING) 2A :nonitor and to revise the surveillance intervals to be consistent with other PING

monitors.

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The replacement monitor is better suited to this application and shouH be able to function properly for longer intervals between functional tests and calibra-tions. The NRC staff reviewed maintenance and calibration data for similar monitors installed at other locations in the facility. They remained within specification at the end of their surveillance interval without intervening maintenance.

1 The proposed change will not affect monitoring requirements, including equipment operability and remedial action statements. Sample frequency and analysis requirements will also remain the same. Effluent release rates to the environ-ment will not be affected. _

CONCLUSION g[0{goh ! 0 Based on the above evaluation, the proposed change is acceptable. It does not reduce safety margins or result in increased effluents to the environment. The impact of this proposed activity falls within the scope of activities previously considered in the program 1 tic environmental impact statement.

Dated: A4ust 30, 1988 Principal Contributor: L. Thonus

ENCLOSURE DOCKET NO. 50-320

Replace the following pages of the TMI-2 Recovery Operations Plan with the enclosed pages.

4.3-5 4.3-7 O

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N TABLE 4.3-3 (Cont'd)

RADIATION MONITORING II4STRUMENTATION SURVEILLANCE REQUIREMENTS -

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m h , CHANNEL MINIMUM g CHANNEL CHANNEL FUNCTIONAL CHANNELS o FUNCTIONAL UNIT CHECK CALIBRATION TEST OPERABLE APPLICABILITY ACTION O

j g 5. FUEL TRANSFER CANAL i Z a.

, Criticality Monitor D R M 1 Note 11 Note 12 1 6. DEL POOL "A"

a. Criticality Monitor D R M 1 Note 11 Note 12

7. FUEL HANDLING BUILDING y TRUCK BAY

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a. Criticality Monitor D R M 'l Note 11 Note 12

8. WASTE HANDLING AND PACKAGING FACILITY

a. Exhaust Monitor D R M 1 Note 1 Note 13

9. REACTOR BUILDING i a. End Fitting Storage D R M 1 Note 14 Note 15

! Area Criticality Monitor y (See following pages ?r Notes.) ,

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N TABLE 4.3-3 (Cont'd)

• N x RADIATION MONITORING INSTRUNENTATION SURVEILLANCE REQUIREMENTS E

m NOTES:

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11. During either of the following 3perations:

, a. Handling of canisters containing core material.*

b. Handling of any heavy load over canisters containing core materials.

12. With less than one channe! operable, teminate the following operations:

a. Handling of canisters containing core material.*

b. Handling of any heavy load over canisters containing core materia,1.

w 13. With less than one channel operable, effluents releases via the affected pathway may continue for up to 4 thirty (30) days provided that samples are continuously collected with auxiliary sampling equipment within the WHPF. These auxiliary filter samples will be changed daily and a gamma scan performed within 24-hours. After completion of the gamma scan, an analysis for gross alpha, gross beta, and'Sr/Y-90 activities will be completed within % honrs.

14. During periods when personnel are in the containment and end fittings are being transferred to or stored in their designated location outside the Reactor Vessel.

15. With less than one channel operable, teminate the following operations:

a. Handling of end fitting storage containers outside the Reactor Vessel.**

b. Handling of any heavy load over the end fitting storage container area.

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1 ***This shall not prohibit placing a canister in transit in a safe storage location.

o This shall not prohibit placing an end fitting storage container in transit in a safe storage location.

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