ML20212Q722

Amend 27 to License DPR-73,revising Tech Specs to Delete All Operability Requirements for Emergency Diesel Generators & Modifying Operability Requirements for Control Room Emergency Air Cleanup Sys

ML20212Q722
Person / Time
Site:	Three Mile Island
Issue date:	04/17/1987
From:	Travers W Office of Nuclear Reactor Regulation
To:
Shared Package
ML20212Q693	List: ML20212Q690 ML20212Q722 ML20212Q734
References
NUDOCS 8704240023
Download: ML20212Q722 (14)

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[ ([,h g.J ,, q E NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 k .%*

GENERAL PUBLIC UTILITIES NtfCLEAR CORPORATION DOCKET N0. 50-320 THREE MILE ISLAND NUCLEAR STATION UNIT NO. 2 AFENDMENT TO FACILITY OPERATING LICENSE Amendment No. 27 License No. DPR-73

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

A. The applications for amendment dated June 18, 1985 and July 31, 1985 as supplemented by letters dated November 20, 1985, February 26, 1986 and May 20, 1986 by General Public Utilities Nuclear Corporation (licensee), comply with standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's regulations set forth in 10 CFP Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the regulations of the Commission; C. There is reasnnable 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 Commission's regulations; 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; E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable reovirements have been satisfied.

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.(2) of Facility Operating License No. DPR-73 is hereby amended to read as follows:

2.C (2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 27 are hereby incorporated in the license. The licensee shall operate the facility in accordance with Technical Specifications and all Commission Orders issued subsequent to March 28, 1979.

8704240023 870417 PDR ADOCK 05000320 P PDR

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

FOR THE NUCLEAR REGULATORY COMMISSION William D. Travers, Director TMI-? Cleanup Project Directorate Division of PWR Licensing-B Office of Nuclear Reactor Regulation Date of Issuance: April 17, 1987

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a 3-ATTACHMENT TO LICENSE AMENDMENT NO. 27 TO FACILITY OPERATING LICENSE NO. DPR-73 DOCKET N0. 50-320 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain a vertical line indicating the area of change.

Amendment Page 3.7-2 3.7-4 3.7-8 3.8-1 3.8-2 3.8-3 3.8-4 3.9-2 3.9-3 B 3/4 7-1 B 3/4 7-2

. -r LIMITING CONDITIONS FOR OPERATION

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3.7.4- NUCLEAR SERVICE RIVER WATER SYSTEM Deleted.

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THREE MILE ISLAND - UNIT 2 3.7-2 Amendment No. 27

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LIMITING CONDITIONS FOR OPERATION 3.7.7 CONTROL ROOM EMERGENCY AIR CLEANUP SYSTEM 3.7.7.1 The Control Room Ventilation and Emergency Air Cleanup System shall be OPERABLE

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a. Two Control Room supply Fans and associated cooling coils,

b. Two Control Room Bypass Fans,

c. One charcoal adsorber and HEPA filter train, and  !

d. Two isolation dampers in the outside air intake duct.  :

e. The Control Room air inlet radiation monitor OPERABLE. ,

APPLICABILITY: RECOVERY MODE ACTION:

a. With one Control Room Supply Fan or its associated cooling coil inoperable, restore the inoperable fan and/or cooling coil to OPERABLE status within 7 days.

b. With one Control Room Bypass Fan inoperable restore the inoperable fan to OPERABLE status within 7 days.

c. With the filter train inoperable', restore the filter train to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

d. With one isolation damper in the outside air intake duct inoperable, restore the inoperable damper to OPERABLE status or close the duct within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by use of at least one isolation damper secured in the closed position.

e. With the Control Room Air Inlet Radiation Monitor inoperable, restore i it to OPERABLE status or place the Control Room Emergency Air Cleanup  ;

System in the recirculation mode of operation within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

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• Standby onsite AC power (emergency diesel generators) is not required for I operability.

THREE MILE ISLAND - UNIT 2 3.7-4 Amendment No. 27

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p .. n LIMITING CONDITIONS FOR OPERATION DELUGE / SPRINKLER SYSTEMS 3.7.10.2 The Deluge and/or Sprinkler Systems located in the following areas shall be OPERABLE:

a. Deleted.

b. Deleted.

c. Air Intake Tunnel (Deluge - 2 of the 3 zones)

d. Hydrogen Purge Exhaust Filter AH-F-34#

e. Reactor Building Purge Exhaust Filters AH-F-31A/B#

f. Control Room Bypass Filter AH-F-5

g. Deleted.

h. Fuel Handling Building Exhaust Filter AH-F-14A/B#

i. Waste gas disposal filter WDG-F-1

j. Auxiliary Building exhaust filters AH-F-10A/B#

k. Southeast Storage Facility ***

APPLICABILITY: RECOVERY MODE.

ACTION:

With one or.more of the above required deluge and/or sprinkler systems inoperable, establish a roving (at least once perhour) fire watch with backup fire suppression equipment for the unprotected area (s) within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />; restore the system to OPERABLE status within 14 days.

• • • This facility's Action Statement shall require a roving fire watch once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> instead of once per hour.

1. Supply line may be isolated by a single manually operated valve.

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THREE MILE ISLAND - UNIT 2 3.7-8 Amendment No. 27 1

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LIMITING CONDITIONS FOR OPERATION 3.8 ELECTRICAL POWER SYSTEMS 3.8.1 A.C. SOURCES

3. 8.1.1 As a minimum, the following A.C. electrical power sources shall be OPERABLE:

a. Two physically independent circuits between the offsite transmission network and the onsite Class 1E distribution system.

b. Deleted APPLICABILITY: REC 0VERY MODE.

ACTION:

a. With one offsite circuit of the above required A.C. electrical power sources inoperable, verify the OPERABILITY of the remaining offsite cir-cuit and demonstrate the OPERABILITY of the D.C. bus trains by performing Surveillance Requirements 4.8.2.2.1 and 4.8.2.3.2.a.4 within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

Restore the full complement of the above required A.C. electrical power sources to OPERABLE status within 7 days.

b. With both offsite circuits of the above required A.C. electrical power sources inoperable, suspend CORE ALTERATIONS and cease movement of heavy loads in the reactor building.* Restore one circuit within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and restore the second A.C. circuit to OPERABLE status within 7 days.

• This does not preclude completion of those activities necessary to place the i plant in a safe configuration.

THREE MILE ISLAND - UNIT 2 3.8-1 Amendment No. 27

TABLE 3.8-1

] TESTING FREQUENCY MATRIX i

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TABLE 3.8-2 RESTORATION TIME MATRIX DELETED .

THREE MILE ISLAND - UNIT 2 3.8-3 Amendment No. 27

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LIMITING CONDITIONS FOR OPERATION

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3.8.2 ONSITE POWER DISTRIBUTION SYSTEMS 3.8.2.1 A.C. DISTRIBUTION 3.8.2.1.a The A.C. electrical busses listed in Section 4.8.2.1.a of the REC 0VERY OPERATIONS PLAN shall be OPERABLE and energized with tie breakers open (unless closed in accordance with procedures approved pursuant to Specifica-tion 6.8.2) between redundant busses.

APPLICABILITY: RECOVERY MODE.

ACTION:

With less than the above complement of A.C. busses OPERABLE, restore the inoperable bus to OPERABLE status within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

3.8.2.1.b The AC electrical busses listed in Section 4.8.2.1.b of the RECOVERY OPERATIONS PLAN shall be OPERABLE and energized.

APPLICABILITY: RECOVERY MODE ACTION:

a. With any of the above A.C. busses incapable of being supplied by its respective inverter, restore that capability to the affected bus within 7 days.

. b. With any of the above A.C. busses de-enerized, restore the inoperable bus to OPERABLE status within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

THREE MILE ISLAND - UNIT 2 3.8-4 Amendment No. 27

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LIMITING CONDITIONS FOR OPERATION

b. With no Fuel Transfer Canal (deep end) water level instruments OPERABLE, tcrminate all activities involving any Canister containing core material in or over the Fuel Transfer Canal (deep end) and/or all activities involving the plenum assembly and all operations involving changes in the Fuel Transfer Canal (deep end) water inventory and restore one inoperable instrument to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

FUEL TRANSFER CANAL (DEEP END) WATER LEVEL 3.9.4 The water level in the Fuel Transfer Canal (deep end) shall be maintained at the level specified per NRC approved procedures.

APPLICABILITY: Whenever any Canister containing core material and/or the plenum assembly is in the Fuel Transfer Canal (deep end).

ACTION:

a. With the Fuel Transfer Canal (deep end) water level not in accordance with approved procedures, terminate all activities involving any Canister containing core material in or over the Fuel Transfer Canal (deep end) and/or all activities involving the plenum assembly and restore the water level to within specification within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

FUEL HANDLING BUILDING / AUXILIARY BUILDING AIR CLEANUP SYSTEMS 3.9.12.1 The Fuel Handling Building Air Cleanup Exhaust System shall be OPERABLE with one of the four system air cleanup exhaust fans OPERABLE.

APPLICABILITY: RECOVERY MODE ACTION:

With the Fuel Handling 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 gaseous radioactive wastes in the Fuel Handling Building (other than sampling evolutions required by the Technical Specifications or RECOVERY OPERATIONS PLAN) until the system is restored to OPERABLE status.

THREE MILE ISLAND - UNIT 2 3.9-2 Amendment No. 27

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LIMITING CONDITIONS FOR OPERATION 3.9.12.2 The Auxiliary Building Air Cleanup Exhaust System shall be OPERABLE with one of the four system air cleanup exhaust fans OPERABLE.

APPLICABILITY: RECOVERY MODE ACTION:

. 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 gaseous radioactive wastes in the Auxiliary Building (other than sampling evolutions required by the Technical Specifications or RECOVERY OPERATIONS PLAN)-until the system is restored to OPERABLE status. -

ACCIDENT GENERATED WATER 3.9.13 Discharge of ACCIDENT GENERATED WATER shall be prohibited until approved by the NRC. ACCIDENT GENERATED WATER shall be discharged in accordance with procedures approved pursuant to Specification 6.8.2.

APPLICABILITY: RECOVERY MODE ACTION:

None except as provided in Specification 3.0.3.

REACTOR BUILDING SUNP WATER 3.9.14 Deleted.

THREE MILE ISLAND - UNIT 2 3.9-3 Amendment No. 27

4 3/4.7 PLANT SYSTEMS

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2 3/4.7.1 FEEDWATER SYSTEM Deleted by Amendment of Order Dated April 1, 1982..

3/4.7.2 SECONDARY SERVICES CLOSED COOLING WATER SYSTEM j Deleted.

J 3/4.7.3 CLOSED CYCLE COOLING WATER SYSTEM l

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3/4.7.3.1 NUCLEAR SERVICES CLOSED CYCLE COOLING SYSTEM 4

Deleted.

3/4.7.3.2 DECAY HEAT CLOSED COOLING WATER' SYSTEM t

Deleted.

3/4.7.3.3 MINI DECAY HEAT REMOVAL SYSTEM (MDHRS)

, Deleted.

3/4.7.4 NUCLEAR SERVICE RIVER WATER SYSTEM i Deleted.

3/4.7.6 FLOOD PROTECTION .

l The limitation on flood protection ensures that facility protective actions will be taken in the event of flood conditions. The limit of elevation of  ;

302 ft. Mean Sea Level USGS datum is the elevation at which facility flood control measures are required to be taken to provide protection to Safety  !

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PLANT SYSTEMS BASES 3/4.7.7 CONTROL ROOM EMERGENCY AIR CLEANUP SYSTEM The OPERABILITY of the control room emergency air cleanup system ensures that

1) the ambient air temperature does not exceed the allowable temperature for continuous duty rating for the equipment and instrumentation cooled by this system and 2) the control room will remain habitable for operations personnel during and following all credible accidents at TMI-2. Under certain conditions (i.e., loss of offsite power combined with a severe accident at Unit 1), it would be required to place TMI-2 in a stable configuration with core alterations suspended. In this case, operability requirements to ensure TMI-2 control room habitability may be temporarily suspended. The OPERABILITY of this system in conjunction with control room design provisions is based on limiting the radia-tion exposure to personnel occupying the control room to 5 rem or less whole body, or its equivalent. This limitation is consistent with the requirements

! of General Design Criterion 19 of Appendix "A", 10 CFR 50.

3/4.7.9 SEALED SOURCE CONTAMINATION The limitation on removable contamination for sources requiring leak testing, including alpha emitters, is based on 10CFR70.39(c) limits for plutonium.

This limitation will ensure that leakage from byproduct, source, and Special Nuclear Material sources will not exceed allowable intake values.

3/4.7.10 FIRE SUPPRESSION SYSTEMS  :

The OPERABILITY of the Fire Suppression Systems ensures that adequate fire suppression capability is available to confine and extinguish fires occurring in any portion of the facility where Safety Related equipment is located.

The Fire Suppression System consists of the water system, spray and/or sprinklers, Halon and fire hose stations. The collective capability of the Fire Suppression Systems is adequate to minimize potential damage to Safety Related equipment and is a major element in the Facility Fire Protection Program. .Any two of the four main fire pumps provide combined capacity greater than 3575 gpm.

4 In the event that portions of the Fire Suppression Systems are inoperable, alternate backup fire fighting equipment is required to be made available in the affected areas until the affected equipment can be restored to service.

In the event that the Fire Suppression Water System becomes inoperable, immediate corrective measures must be taken since this system provides the majorfiresuppressioncapabilityoftheplant. The requirement for a Special Report to the Commission provides for timely evaluation of the acceptability of the corrective measures to provide adequate fire suppression capability for the continued operation of the nuclear plant.

l THREE MILE ISLAND - UNIT 2 B 3/4 7-2 Amendment No. 27

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