ML20073M060
| ML20073M060 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 04/15/1983 |
| From: | Mittl R Public Service Enterprise Group |
| To: | Schwencer A Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737 GL-82-33, NUDOCS 8304210402 | |
| Download: ML20073M060 (7) | |
Text
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9 O PSI G PubhcService Electric and Gas e
Company 80 Park Plaza, Newark, NJ 07101/ 201430 7000 MAILING ADDRESS / P.O. Box 570 Newark, NJ 07101 April 15, 1983 Director of Nuclear Reactor Regulation U.S.
Nuclear Regulatory Commission 7920 Norfolk Avenue Bethesda, Maryland 20014 Atte n:
Mr. Albert Schwencer, Chief Licensing Branch 2 Division of Licensing Gentlemen:
HOPE CREEK GENERATING STATION DOCKET NO. 50-354 GENERIC LETTER 82-33 Pursuant to Generic Letter 82-33, Supplement 1 to NUREG-0737 - Requirements for Emergency Response Capability, Public Service Electric and Gas Company is forwarding the attached schedule information for completing the basic re-quirements of each of the items identified in NUREG-0737, Supplement 1.
The dates indicated herein are subject to modification due to incorporation of ongoing BWR Owners Group program recommendations and equipment delivery schedules.
If you require additional information, do not hesitate to contact us.
Very t ly you s, f
/
y R. L. Mittl General Manager -
Nuclear Assurance and Regulation DJD: cag Attachment A, B, C, D& E d
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Mr.
D. H. Wagner USNRC Licensing Project Manager l
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W. H. Bateman USNRC Senior Resident Inspector hD fgerj N.6 Ipr 8304210402 830415 PDR ADOCK 05000354 p
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A.
SAFETY PARAMETER DISPLAY SYSTEM ( S PDS )
SPDS. design will be finalized by February 1984, at which time a safety analysis describing the basis for all selected parameters will be provided.
The SPDS is scheduled to be operable by June, 1985.
The SPDS will be factored into the overall control room design rev iew scheduled to begin August 12, 1983, (See Attachment B, Figure B-1).
Any additional SPDS recommendations resul-ting from the BWR Owner's Group's ongoing program will be evaluated for applicability to Hope Creek Generating Station.
The present SPDS design is discussed in Hope Creek Generating Station Final Safety Analysis Report Section 7.5.
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B.
DETAILED CONTROL ROOM DESIGN REVIEW Figure B-1 provides a detailed schedule for completing the actions necessary to comply with the basic require-ments for a detailed control room design rev iew.
A program plan will be submitted by October 12, 1983.
A summary report will be submitted by August 15, 1984, and will include a schedule for implementation of resulting design changes.
Detailed discussions of the Hope Creek Generating S tation control room design review will be incorporated in amendments to Chapter 18 of the Final Safety Analysis Report.
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o FIGURE B-1 j
j TMI LD.1 CONTROL ROOM DESIGN REVIEW FIELD REVIEW CONSULTANT TO BECHTEL REVISE DRAWINGS IMPLEMENT EVALUATE RECOMMENDATION DEVELOP TO REVIEW TASKS 1 TOIMPLEMENT DESIGN DESIGN CHANGEN CHANGES OUT FOR BID BIDS
, AND AWARD PROGRAM PLAN PROGRAM PLAN THRU 9 n
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2/28/83A 4/11/83 4/24/83 8/12/83 8/15/84 10/1/84 12/84
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w TASKS
- 1) DEVELOP DETAILED SCHEDULE
- 2) CONDUCT OPERATING EXPERIENCE REVIEW
- 3) DEVELOP C/R INVENTORY
- 4) SYSTEM FUNCTIONAL REVIEW AND TASK ANALYSIS
- 5) CONDUCT C/R SURVEYS
- 6) VERIFICATION OF TASK PERFORMANCE CAPABILITIES
- 7) VAllDATION OF C/R FUNCTIONS
- 8) HUMAN ENGINEERING DISCREPANCY (HED) ASSESSMENT
- 9) FINAL REPORT NOTES:
- DESIGN CHANGES TO BE IMPLEMENTED WILL BE BASED ON SCOPE OF llED'S AND COMPLEXITY OF ACCOMPLISHMENT.
- 1) 12/82 DATE PER BLP 13878
- 2) THIS ITEM ASSUMED TO BE AN EXCLUSION FROM THE TURNOVER OF THE CONTROL COMPLEX FOR INTEGRATED TESTING (INCENTIVE FOR MILESTONE NO. 4) l
C.
Regulatory Guide 1.97 - Application to_ Emergency Response Facilities Hope Creek Generating Station Final Safety Analysis Re-port Section 1.8 describes compliance to Regulatory Guide 1.97, Revision 2.
Final Safety Analysis Report Section 7.5 provides additional details on the control room integrated display system, and the emergency re-sponse facilities display systems provided in the tech-nical support center and emergency operations facility.
Final Safety Analysis Report Table 7.5-1 lists the para-meters from Table 1 of Regulatory Guide 1.97 that are displayed by the control room integrated display system and the emergency response facilities display systems.
This table also provides the information required to be submitted in a report under Section 6.2 of Supplement 1 to NUREG-0737.
The control room integrated display equipment is scheduled for installation by December 1983.
D.
UPGRADE EMERGENCY OPERATING PROCEDURES (EOPs)
All emergency procedures will be written following the guidelines of INPO 82-017, Emergency Operating Procedure Writing Guidelines, and the guidelines of the BWR Owners Group-Emergency Procedures Committee, as long as the guide-lines do not contradict existing NRC directives.
Correc-tions will be made, as necessary, based on NRC audits of these procedures.
A procedures package will be submitted to NRC by January 1985.
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E.
EMERGENCY RESPONSE FACILITIES.
The Hope Creek Generating Station Technical Support Center, Operations Support Center, and Emergency Operations Facility are designed to support emergency operation and meet the intent 'of the requirements of NUREG-0737.
These facilities are scheduled to be completely _ functional by June 1985.
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