ML20062K095

Amend 47 to License DPR-73,deleting Definition of Agw & Current App TS Limiting Condition of Operation Re Disposal of Agw Using Processed Water Disposal Sys

ML20062K095
Person / Time
Site:	Crane
Issue date:	12/06/1993
From:	Dudley R Office of Nuclear Reactor Regulation
To:
Shared Package
ML20062K089	List: ML20062K082 ML20062K095 ML20062K104
References
NUDOCS 9312140419
Download: ML20062K095 (8)

Text

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E i E UNITED STATES l

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NUCLEAR REGULATORY COMMISSION Y,

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WASHINGTON, D.C. 2055H001 g,p GPU NUCLEAR CORPORATION DOCKET NO. 50-320 THREE MILE ISLAND NUCLEAR STATION. UNIT NO. 2 POSSESSION ONLY LICENSE s

Amendment No. 47 License No. DPR-73 i

1.

The U.S. Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment filed by GPU Nuclear Corporation (the licensee) dated August 5,1993, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),

and the regulations of the Commission as set forth.in 10 CFR Chapter I; The facility will be maintained in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the regulations of the Commission; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of t

the regulations of the Commission and all applicable requirements have been satisfied.

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f 9312140419 931206 PDR ADOCK 05000320 P

PDR

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C(l) of Possession Only License No. DPR-73 is hereby amended to read as follows:

(1) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 47, are hereby incorporated into this license. The licensee shall maintain the facility in accordance with the Technical Specifications and all Commission Orders issued subsequent to the date of the possession only license.

3.

This license amendment is effective as of the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION N dc Richard F. Dudley, Act ig Director Non-Power Reactors and Decommissioning Project Directorate Division of Operating Reactor Support Of fice of Nuclear Reactor Regulation

Enclosure:

Changes to the Technical Specifications Date of Issuance: December 6, 1993 4

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ENCLOSURE TO LICENSE AMENDMENT NO. 47 i

P_QSSESSION ONLY LICENSE NO. DPR-73 t

DOCKET N0 50-320 j

Replace the following pages of the Appendix A Technical Specifications with the attached pages. The revised pages are identified by amendment number and contain vertical lines indicating the area of change.

i Remove Insert l-5 1-5 1-6 1-6 3.9-3 3.9-3 i

3.9-4 3.9-4 i

B 3/4 9.1 B 3/4 9-1

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1.0 DEFINITIONS CORE ALTERATION i

1.15 CORE ALTERATION shall be the movement or manipulation of any reactor component (including fuel) within the reactor pressure vessel with the vessel head removed and fuel in the vessel. Suspension of CORE ALTERATION shall not preclude completion of movement of a component to a safe conservative position.

LOSS-TO-AMBIENT r

1.16 LOSS-TO-AMBIENT is a passive cooling mode by which decay heat, generated by the reactor core, is removed and transferred to the surrounding environment by air and passive components (i.e., Reactor Vessel) inside the Reactor Building.

ACCIDENT GENERATED WATER 1.17 Deleted 1.18 UCENSED Ol'ERATOR (OD - any individual who posse;ses an NRC Operator's license i

pursuant to Title 10, Code of Federal Regulations, Part 55, "O,)erators Licenses."

1.19 SENIOR LICENSED OPERATOR (SOL) - any individaal who possesses an NRC Senior Operator's license pursuant to Title 10, Code of Federal Regulations, Part 55, " Operators Licenses."

1.20 FUEL HANDLING SENIOR LICENSED OPERATOR (SOL-FID - an individuallicensed by the Nuclear Regulatory Commission to supervise fuel handling and core alterations operations.

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l THREE MILE ISLAND - UNIT 2 1-5 Amendment No. 47

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1.0 DEFINITIONS 1.21 CONTAINMENT ISOLATION shall exist when:

a.

Each penetration is:

1.

Closed by an accessible manual valve, a welded or bolted blind flange, or a deactivated automatic valve secured in the closed position to provide isolation of each penetration, or; I

2.

Open per an approved procedure but can be closed pursuant to Specification 1.21.a.1. Controls shall be implemented to minimize the time the penetration is allowed open and to specify the conditions for which the penetration is open. Penetrations shall be expeditiously closed upon completion of the conditions specified in the appmved pmcedures.

b.

The Equipment Hatch is closed and sealed, c.

Each Containment Airlock is OPERABLE pursuant to Specification 3.6.1.6.

1.22 The OFFSITE DOSE CALCULATION MANUAL (ODCM) shall contain the methodology and parameters used in the calculation of offsite doses resulting from radioactive gases and liquid effluents, in the calculation of gaseous and liquid effluent monitoring Alarm / Trip Setpoints, and in the conduct of the Environmental Radiological Monitoring Pmgram. The ODCM shall also contain (1) the Radioactive Effluent Controls and Radiological Environmental Monitoring Programs required by Section 6.8.4 and (2) descriptions of the information that should be included in the Annual Radiological Envimnmental Operating Repon and the Annual Radioactive Effluent Release Repon required by Specifications 6.9.1.1 and 6.9.1.2, respectively.

1.23 MEMBER (S) OF THE PUBLIC shall include all persons who are not occupationally associated with the plant. This category does not include employees of the GPU System, GPU contractors or vendors. Also excluded from this category are persons who enter the site to service equipment or to make deliveries.

1.24 UNRESTRICTED AREA shall be any area at or beyond the SITE BOUNDARY access which is not controlled by the licensee for purposes of protection of individuals from exposure to radiation and radioactive materials, or any area within the SITE BOUNDARY used for i

residential quarters or for industrial, commercial, institutional, and/or recreational purposes.

1.25 SITE BOUNDARY shall be that line beyond which the land is neither owned, nor leased, nor otherwise controlled by GPU Nuclear.

1.26 Deleted.

THREE MILE ISLAND - UNIT 2 1-6 Amendment No. 47

i IDfITING CONDITIONS FOR OPERATION ~

AUXIUARY BUILDING AIR CLEANUP EXHAUST SYSTEM

- 3.9.12.2 The Auxiliary Building Air Cleanup Exhaust System shall be OPERABLE with one of l

the four system air cleanup exhaust fans OPERABLE.

APPLICABILITY:

MODES 1,2 and 3 ACTION:

i With the Auxiliary Building Air Cleanup Exhaust System inoperable, restore the system to operable status within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or suspend all operations involving movement of liquid and solid radioactive wastes in the Auxiliary Building (other than sampling evolutions required by the Technical Specifications or RECOVERY OPERATIONS PLAN), the release of which could exceed 50% of the Appendix B Technical Specification instantaneous release rate for gaseous i

efnuents, until the system is restored to OPERABLE status.

ACCIDENT GENERATED WATER 3.9.13 Deleted l

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1 THREE MILE ISLAND - UNIT 2 3.9-3 Anendrent No. 47 l

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TABLE 3.9-1 t

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l THREE MILE ISLAND - UNIT 2 3.9-4 Amendment No. 47

P 3/4.9 RADIOACTIVE MATERIALS STORAGE 1

BASES 3/4.9.1 SPENT FUEL STORAGE POOL "A" WATER LEVEL MONITORING Spent Fuel Storage Pool "A" Water Level Monitoring instmmentation has been pmvided to assure the capability to monitor water level in the Spent Fuel Storage Pool "A".

3/4.9.2 SPENT FUEL STORAGE POOL "A" WATER LEVEL The water level in the Spent Fuel Storage Pool "A" has been established to limit the dose rate, due to the storage of Canisters, to acceptable levels.

3/4.9.3 FUEL TRANSFER CANAL (DEEP END) WATER LEVEL MONITORING Fuel Tmnsfer Canal Water Level Monitoring instn mentation has been provided to assure the capability to monitor water level in the deep end of de Fuel Transfer Canal.

3/4.9.4 FUEL TRANSFER CANAL (DEEP END) WATER LEVEL The water level in the Fuel Transfer Canal (deep end) has been established to limit the dose rate, due to the storage of the plenum assembly and Canisters, to acceptable levels.

3/4.9.12 FUEL HANDLING BUILDING /AUXTLIARY BUILDING AIR CLEANUP SYSTEM The requirement for the Fuel Handling Building / Auxiliary Building Air Cleanup System to be operating or OPERABLE ensures that radioactive material released to these buildings will be filtered through the HEPA filters prior to release to the atmosphere. In the event the systems are not restored to OPERABLE status within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, the Technical Specifications require the suspension of any liquid or solid radioactive waste handling, the release of which could exceed 50% of the instantaneous release rate limits for gaseous effluents specified in Section 2.1.2 of the Appendix B Technical Specifications. These restrictions correspond to solid radioactive waste with a total activity of greater than I curie of particulates with half-lives greater than eight (8) days and liquid radioactive waste with an activity greater than 0.5 curies of paniculates with half-lives greater than eight (8) days.

r 3/4.9.13 ACCIDENT GENERATED WATER Deleted THREE MILE ISLAND - UNIT 2 B 3/4 9-1 Amendment No. 47