ML19260C364
| ML19260C364 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 12/17/1979 |
| From: | Hancock J FLORIDA POWER CORP. |
| To: | Reid R Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML19260C365 | List: |
| References | |
| 3--3-A-3, 3-0-3-A-3, NUDOCS 7912260245 | |
| Download: ML19260C364 (5) | |
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NM Power CO 4 PO R A T BON December 17, 1979 File:
3-0-3-a-3 Mr. Robert W. Reid Chief Operating Reactors Branch #4 Division of Operating Reactors U.S. Nuclear Regulatory Commission Washington, D.C. 20555
Subject:
Crystal River Unit 3 Docket No. 50-302 Operating License No. DPR-72 Fire Program Modifications
Dear Mr. Reid:
Your letter of September 11, 1979 requested Florida Power Corporation to submit additional information concerning the alternate safe shutdown capability modification proposed for Crystal River Unit 3.
In that regard, Florida Power Corporation hereby submits for review the additional information requested in the enclosure of your letter.
If you wish to discuss our response further or if you require additional information, please contact us.
Very truly yours, FLORID POWER CORPORATION
/
1617 238
. A. Hancock Director, Nuclear Operations Simpson(CR3FireMod)DN87
'7 2Y khM51 General Office 3201 Tnirty-fourtn street soutn. P O Box 14042. St Petersburg da 33733.
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STATE OF FLORIDA COUNTY OF PINELLAS J. A. Hancock states that he is the Director, Nuclear Operations, of Florida Power Corporation; that he is authorized on the part of said company to sign and file with the Nuclear Regulatory Commission the information attached hereto; and that all such statements made and matters set forth therein are true and correct to the best of his knowledge, information and belief.
. A. Hancock Subsccibed and sworn to before me, a Notary Public in and for the State and County above named, this 17th day of December, 1979.
Notary Public Notary Public, State of Florida at Large, My Commission Expires: August 8, 1983
)fjJg CameronNotary 3(D12)
FPC RESPONSE TO NRC REQUEST FOR ADDITIONAL INFORMATION Response to Item 8a: Systems and port 'ons thereof required for safe shutdown are tabulated in Attachment A, with appropriate FSAR system descriptive references. Equipment required for hot and/or cold shutdown is discussed in de-tail, along with proposed modifications to achieve remote shutdown f rom outside the control room. Response to Item 8b: The proposed.Ramote Shutdown System configuration is shown on Attach-ment B. This drawing shows the relative location of normal and remote shutdown control devices, instrumentation, and cable routings. Pro-posed modifications of equipment and cable routings to divorce safe shutdown control completely from the control room area are shown on this drawing. Response to Item 8c: Equipment modifications for the Remote Shutdown System will not degrade safety systems. New isolation switches and control switches will meet the design criteria and standards in the FSAR, and alarms will be provided in the control room whenever isolation switches are used to assume remote control. Electrical separation and seismic sup-port criteria for safety circuits are in accordance with the design criteria and standards in the FSAR. Response to Items 8d and 8e: All instrumentation and control equipment at the Remote Shutdown Areas in the Engineered Safeguards Switchgear Rooms utilize power indepen-dent of the control room area, and associated cables do not pass through the cable spreading area, as shown on Attachment B. Isolation devices are provided on the control circuits that are routed through the Cable Spreading Room as shown on Attachment B. Response to Item 8f: There is presently a procedure in effect at CR #3, EP-113 - Plant Shutdown From Outside Control Center, which describes the tasks to be performed to safely shutdown the unit from outside the Control Center. This procedure presently reflects the existing CR #3 design. This procedure will be revised to include the Remote Shutdown System once the design and installation of this modification is complete. Response to Item 8g: Spare control circuit fuses for switchgear and MCCs needed for shut-down of the plant from outside of the Control Center will be located near or at the existing fuses. A list of this equipment is being developed. The shutdown procedure is being revised such that in the event that shutdown from outside the Control Center is required, the operator is to check and/or replace these fuses if the equipment is inoperable. Simpson(CR3FireMod)DN87 1617 240
Response to Item 8h: The following positions at CR #3 make up the shif t compliment: Shift Supervisor Nuclear Auxiliary Operator Assistant Shift Supervisor Assistant Nuclear Auxiliary Chief Nuclear Operator Operator Nuclear Operator Chem / Rad personnel 2 Assistant Nuclear Operators Guard personnel The following positions are responsible for shutdown of the unit per EP-113 which is being revised: Shift Supervisor Chief Nuclear Operator Nuclear Operator Assistant Nuclear Operator (Plant ) Assistant Nuclear Operator (Control Center) The following positions normally comprise the 5-man Fire Brigade at CR #3: Assistant Shift Supervisor Nuclear Auxiliary Operator Assistant Nuclear Auxiliary Operator Chem / Rad Technician Security Guard EM-101, Fire Protection Plan, and EM-216, Duties of the Nuclear Plant Fire Brigade, define the responsibility of the Fire Brigade members at CR #3. Response to Item 81: Detailed test procedures will be perf ormed to demonstrate control switch operation only from the selected position of the isolation switch and not from the unselected position, and that the control room alarm is actuated when the isolation switch (s) is in the local position. Response to Item 8j: Technical Specifications will be revised to include surveillance requirements for the isolation and new control equipment. Response to Item 8k: The systems required to perform hot and cold shutdown from outside the control room are discussed in Attachment A, and are those listed in Section 7.4.6 of the FSAR. The modifications discussed in Attach-ment A provide remote shutdown capability in event of a control room area fire. 1617 241 Simpson(CR3FireMod)DN87
Response to Item 81: The repair of major components are covered by specific or general repair procedures MP-101 through MP-408. The repairs to those systems required for cold shutdown can be accomplished at CR #3. 1617 242 Simpson(CR3FireMod)DN87}}