ML20209D519

Application for Amend to License DPR-50,consisting of Tech Spec Change Request 169,revising Tech Specs to Reflect Fire Protection Instrumentation & Fire Suppression Sys Installed to Satisfy 10CFR50 App R Requirements.Fee Paid

ML20209D519
Person / Time
Site:	Three Mile Island
Issue date:	01/28/1987
From:	Hukill H GENERAL PUBLIC UTILITIES CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20209D525	List: ML20209D519 ML20209D578
References
5211-87-2004, NUDOCS 8702040499
Download: ML20209D519 (9)

Text

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• GPU Nuclear Corporation Nuclear  :: o = s: r 8o Middletown, Pennsylvania 17057 0191 717 944-7621 TELEX 84 2386 Writer's Direct Dial Nurnber:

January 28, 1987 5211-87-2004 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555

Dear Sir:

Three Mile Island Nuclear Station, Unit 1, (THI-1)

Operating License No. DPR-50 Docket No. 50-289 Technical Specification Change Request No.169 Enclosed is one original and thirty-seven conformed copies of Technical Specification Change Request No.169.

Also enclosed is one signed copy of the Certificate of Service for this ,

request to the chief executives of the township and county in which the facility is located, as well as the Bureau of Radiation Protection.

This application requests that the THI-l Technical Specifications be revised to reflect the fire protection instrumentation and fire suppression systems installed to satisfy 10 CFR 50 Appendix R requirements, to clarify Control Building detector locations, as well as reflect additional control room detectors installed for Appendix R and BTP APCSB 9.5-1 Appendix A, to correct a typographical error in Technical Specification Section 3.18.7 and to correct an editorial error in 3.18.7 BASES.

Pursuant to 10 CFR 50.91(a)(1), we enclose our analyses, using the standards in 10 CFR 50.92 of significant hazards considerations. As stated above, pursuant to 10 CFR 50.91(a) of the regulations, we have provided a copy of this letter, the proposed change in Technical Specifications, and our analyses of significant hazards considerations to Thombs Gerusky, the designated representative of the Commonwealth of Pennsylvania, b> p d 0$

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GPU Nuclear Corporation is a subsidiary of the General Public Utilities Corporation

5211-87-2004 January 28, 1987 Pursuant to the provisions of 10 CFR 170.21, enclosed is a check for $150.00 as payment of the fee associated with Technical Specification Change Request No. 169.

Sincerel ,

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Vice President & Director, TMI-1 HDH/DJD/pa/17579

Enclosures:

1) Technical Specification Change Request No.169 ,.

2) Certificate of Service for Technical Specification Change Request No.169 ,

3) Check No. 257607 '

cc: J. Stolz J. Thoma T. Murley F. Young l

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METROPOLITAN EDISON COMPANY JERSEY CENTRAL POWER & LIGHT COMPANY AND PENNSYLVANIA ELECTRIC COMPANY THREE MILE ISLAND NUCLEAR STATION, UNIT 1 Operating License No. DPR-50 Docket No. 50-289 Technical Specification Change Request No.169 This Technical Specification Change Request is submitted in support of Licensee's request to change Appendix A to 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:

Vice Presldent & Director, TMI-l Sworn and Subscribed to before me this d 84 l

- day of Gamf ad ,1987.

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UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION IN THE MATTER Or DOCKET NO. 50-289 LICENSE NO. DPR-50 GPU NUCLEAR CORPORATION This is to certify that a copy of Technical Specification Change Request No.169 to Appendix A of the Operating License for Three Mile Island Nuclear Station Unit 1, has, on the date given below, been filed with executives of Londonderry Township, Dauphin County, Pennsylvania; Dauphin County, Pennsylvania; and the Pennsylvania Department of Environmental Resources, Bureau of Radiation Protection by deposit in the United States mail, addressed as follows:

Mr. Jay H. Kcpp, Chairman Mr. Frederick S. Rice. Chairman Board of Supervisors of Board of County Commissioners Londonderry Township of Dauphin County R. D. #1, Geyers Church Road Dauphin County Courthouse Middletown, PA ~17057 Harrisburg, PA 17120 Mr. Thomas Gerusky, Director PA. Dept. of Environmental Resources Bureau of r,adiation Protection P.O. Box 21163 Harrisburg, PA 17120 GPU NUCLEAR CORP 0 RATIO BY:

Vide Prssi dent & Director, TMI-l DATE: Ja nuary 28, 1987 i

e I. TECHNICAL SPECIFICATION CHANGE RE0 VEST (TSCR) NO. 169 GPUN requests that the following changed replacement pages be inserted into the existing Technical Specifications:

Revised pages: 3-87, 3-87a, 3-89, 3-94 These pages are attached to this change request.

II. REASON FOR CHANGE The TMI-1 Fire Detection System in the Auxiliary, Fuel Handling, Intermediate and Control Buildings and the Fire Suppression System in the Auxiliary Buf1 ding are being expanded to satisfy the commitments made concerning 10 CFR 50 Appendix R and approved in NRC Safety Evaluations dated June 4,1984 and December 30, 1986. The scope changes  %

due to Appendix R modifications are as follows:

1) The existing fire detection system in the Auxiliary Building is being expanded to monitor an additional area of the hallway on elevation 281' in fire zone AB-FZ-5 (Table 3.18-1, Item 10).

2) The existing fire detection system currently installed in the Control Building elevation 306' is being expanded to monitor fire zone FH-FZ-6, the chiller room elevation 285' (Table 3.18-1, Item 4).

3) The existing fire detection system currently installed in the Intermediate Building (IB) is being expanded to monitor the hallway portion of fire zone IB-FZ-4 on elevation 295' (Table 3.18-1, Item 12).

4) The existing fire detection system in the Control Building is being expanded to monitor the emergency feedwater cabinets located in the Control Room (Table 3.18-1, Item 1). This modification is to satisfy commitments made concerning NRC BTP APCSB 9.5-1 Appendix A.

5) The Auxiliary Building fire detection system on elevation 281' and 305' is being revised to reflect the existing cross zone detection configuration by dividing Zone 1 into Zone 1A and Zone 1B (Table 3.18-1, Items 10 and 11).

6) The manually actuated deluge water spray system in AB-FZ-5 (Auxiliary Building containment penetration area at elevation 281')

is converted to an automatically actuated preaction sprinkler system. A water curtain system is being installed to separate redundant equipment in AB-FZ-6 at elevation 305' (Section 3.18.3.1.1).

Techmcal Specification Table 3.18-1. Items 1, 4,10,11 and 12 (pages 3-87 and 3-87a), and Technical Specification Section 3.18.3.1, Item 1 (page 3-89) are revised to incorporate the changes above.

Technical Specification Table 3.18-1, item 1, Control Building Elevation 355', is also being revised to clarify the locations of the existing detectors and increase the minimum number of detectors required to be operable in the control room area and the control room cabinets, as well as incorporate the additional detectors in the emergency feedwater panels (Iten II.4 above).

The Control Building Elevation 355' was equipped with a total of 27 detectors as reflected in the existing Technical Specification Table 3.18-1. These were the 17 detectors in the control room, consisting of 8 control room area detectors and 9 detectors in the HCV, CC & CR, PC &

PCR and PL Panels, and 10 separate detectors in the computer room (i.e.,

total 27).

As part of the Appendix R modifications, 2 additional detectors are being provided in the emergency feedwater (EF) panels. This results in a revised total number of deteators in the Control Building Elevation 355' of 29. These are the 19 detectors in the control room, consisting of 8 control room area detectors, as stated above,11 panel detectors (9 detectors in the HCV, CC & CR, PC & PCR and PL Panels, as stated above, and 2 new detectors in the EF Panels) and 10 separate detectors in the computer room, also as stated above (i.e., total 29).

These detector locations are specifically identified in the proposed amendment as the Control Room Cabinet detectors, Control Room Area detectors, IAC (liod Comp Computer Halon) detectors and I&C (Mod Comp Area) detectors. The existing Technical Specification combines these specific detector locations under the general area locations called Control Room and Computer Room. The total number of detectors in all four specific locations specified in the proposed amendment is 29, as described above (11 detectors in the control room cabinets, 8 detectors in the control room area, and 10 detectors-in the I&C Computer Room).

The minimum number of detectors operable for the Control Room in the existing Technical Specification was 8 This consisted of the 6 detectors listed in the existing Technical Specifications for the cabinets and 2 detectors in the Control Room Area. The minimum number of detectors operable in the proposed amendment is 11 for the Control Room Cabinets and 4 for the Control Room Area. Therefore, the proposed amendment increases the minimum number of detectors required to be operable for the Control Room Cabinets and for the Control Room Area.

The minimum number of detectors operable.for the Computer Room in the existing Technical Specification is 5. The minimum number of detectors operable in the proposed amendment is also 5 for the computer room.

Therefore, the proposed amendment does not change the number of detectors required to be operable in the Computer Room.

The following tabulation is provided to aid in summarizing the changes to the number of detectors provided and the minimum required to be operable for each location in Control Building Elevation 355'.

Exi sting Technical Proposed Specification Amendment No. of Minimum No. of Minimum Detectors Operable Detectors Operable i Control Room Area 8 2 8 4 Control Rs.

Control Room Panels 9 6 11 11 Computer Room 10 5 10 5 t

Total 27 13 29 20 Technical Specification Section 3.18.7 is being revised to correct a typographical error in the spelling of " dampers". The BASES for Technical Specification Section 3.18.7 is also corrected to delete reference to a roving fire watch. This change is an edi.torial correction to be consistent with Specification Section 3.18.7.2a which provides a requirement for a continuous fire watch only. It should be noted that this change was to have been incorporated in a supplement to Technical Specification Change Request No. 97, Rev. I submitted to NRC July 12,1984 (GPUN letter 5211-84-2152).  ;

III. SAFETY EVALUATION JUSTIFYING CHANGE Additional fire detection instrumentation and suppression has been installed to satisfy 10 CFR 50 Appendix R requirements, as defined in the TMI-1 Fire Hazards Analysis Report and Appendix R Section III.G Safe Shutdown Evaluation (FHAR).

This additional fire protection instrumentation and suppression is being added to the existing TMI-1 fire protection Technical Specifications to ensure the operability of the fire protection systems defined in the ,

TMI-1 FHAR. This operability ensures that adequate warning capability is available for the prompt detection of fires and that adequate fire suppression capability is available to confine and extinguish fires and to minimize potential damage to safety-related equipment.

The clarification of Technical Specification Table 3.18-1, Item 1, Control Building Elevation 355', specifically defines detector location and increases the minimum number of detectors required to be operable in the Control Room Cabinets and the Control Room Area. Specifically, defining the detector locations has no impact on nuclear safety or safe slant operation. Increasing the minimum number of detectors required to

>e o>erable provides additional assurance that adequate warning r capa)flity is available for the prompt detection of fires in those areas.

The revision to Technical Specification Section 3.18.7 and 3.18.7 BASES are typographical / editorial corrections only and have no impact on nuclear safety or safe plant operations, i l

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r IV. NO SIGNIFICANT HAZARDS CONSIDERATIONS GPUN has determined that this Technical Specification Change Request poses no significant hazards as defined by NRC regulations in 10 CFR 50.92.

1. Operation of the facility in accordance with the proposed amendment would not involve a significant increase in the probability of occurrence or consequences of an accident previously evaluated.

The design basis event related to this change is a fire in the affected fire zones. The proposed amendment has no affect on the probability of occurrence of this design basis event. The potential consequences of a fire in the affected fire zones are reduced because the proposed change provides additional assurance that the fire detection instrumentation and suppression provided in each fire zone is operable and therefore capable of promptly detecting, confining and extinguishing the fire.

2. Operation of the facility in accordance with the proposed amendment would not create the possibility of a new or different kind of accident from any accident previously evaluated. The design basis event related to this change is a fire in the affected fire zones.

The proposed amendment has no affect on the possibility of creating a new or different kind of accident from any accident previously evaluated. The proposed amendment provides additional assurance that the fire detection instrumentation and suppression systems installed to satisfy 10 CFR 50 Appendix R requirements, as evaluated in the TMI-1 FHAR, are operable and is unrelated to the possibility of creating a new or different kind of accident.

3. Operation of the facility in accordance with the proposed amendment would not involve a significant reduction in a margin of safety.

The proposed amendment provides for the control of the additional fire detection instrumentation and suppression installed to satisfy 10 CFR 50 Appendix R requirements, as evaluated in the TMI-l FHAR.

The proposed amendment also increases the minimum number of detectors required to be operable in the Control Room Cabinets and the Control Room Area in Control Building Elevation 355'.

Therefore, the overall margin of safety for the plant is increased.

The Commission has provided guidelines pertaining to the application of the three standards by listing specific examples in 48 FR 14870. The proposed amendment is considered to be in the same category as examples (1), (ii) and (vii) of amendments that are considered not likely to involve significant hazards consideration in that the proposed changes are purely adninistrative to correct a typographical error and change detector location nomenclature, constitutes an additional control not presently included in the Technical Speciffcations, and is also a change to make a license conform to changes in the regulations.

V. IMPLEMENTATION It is requested that the amendment authorizing this change become effective upon startup following the Cycle 6 refueling outage.

VI. AMENOMENT FEE (10 CFR 170.21)

Pursuant to the provisions of 10 CFR 170.21, attached is a check for

$150.00.