ML20116D344
| ML20116D344 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 04/22/1985 |
| From: | Mittl R Public Service Enterprise Group |
| To: | Schwencer A Office of Nuclear Reactor Regulation |
| References | |
| TASK-2.K.3.18, TASK-TM NUDOCS 8504290388 | |
| Download: ML20116D344 (8) | |
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Pubhc Senace PS Electne and Gas Company 80 Park Plaza Newark, NJ 07101/ 201430-8217 MAILING ADDRESS / P.O. Box 570, Newark, NJ 07101 Robert L. Mitti General Manager Nuclear Assurance anc; Regulation April 22, 1985 Director of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission 7920 Norfolk Avenue Bethesda, MD 20814 Attention:
Mr. Albert Schwencer, Chief Licensing Branch 2 Division of Licensing Gentlemen:
SAFETY EVALUATION REPORT OPEN AND CONFIRMATORY ITEM STATUS HOPE CREEK GENERATING STATION DOCKET NO. 50-354 is a current list which provides a status of the open and confirmatory items identified in Sections 1.~/
and 1.8 of the Safety Evaluation Report (SER).
Items iden-tified as " complete" are those for which PSE&G has provided responses and no confirmation of status has been received from the staff.
We will consider these items closed unless notified otherwise.
In order to permit timely resolution of items identified as " complete" which may not be resolved to the staff's satisfaction, please provide a specific description of the issue which remains to be resolved.
Enclosed for your review and approval (see Attachment 3) are the resolutions to the SER items listed in Attachment 2.
This information will be incorporated, as required, into Amendment 11 of the HCGS FSAR.
Should you have any questions or require any additional information on these items, please contact us.
Very truly yours, k.NEN jf$
8504290380 850422 PDR ADOCK 05000354 E
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9 Director of Nuclear Reactor Regulation 2
4/22/85 C.
D.
H. Wagner USNRC Licensing Project Manager (w/ attach.)
A.
R.
Blough USNRC Senior Resident Inspector (w/ attach.)
M P84 154/04 1/2 l
9-s Datet 4/22/85 ATTACHMENT 1 R.
L.
Mittl to A. Schwencer Item No.
Subject Status ltr. dated OI-l Riverborne Missiles Partial Response 1/31/85 & 2/22/85 OI-2 Equipment Qualification Partial Response 2/1/85, 2/20/85,
& 2/28/85 OI-3 Preservice Inspection Program Partial Response 2/14/85 & 3/19/85 OI-4 GDC 51 Compliance Complete 3/12/85 5 Solid-State Logic Modules Open OI-6 Postaccident Monitoring Open Instrumentation OI-7 Minimum Separation Between Completed 4/4/85 Non-Class IE Conduit and Class IE Cable Trays OI-8 Control of Heavy Loads Closed 1/18/85 (SSER 1) 01-9 Alternate and Safe Shutdown NRC Action OI-10 Delivery of Diesel Generator Closed Amendment 8 Fuel Oil and Lube Oil (SSER 1) 01-11 Filling of Key Management Open Positions OI-12 Training Program Items (a)
Initial Training Program Completed 1/7/85 (b)
Requalification Training Completed 12/28/84 Program (c)
Replacement Training Completed 1/7/85 Program (d)
TMI Issues I.A.2.1, Completed 1/7/85 I.A.3.1, and II.B.4 (e)
Nonlicensed Training Completed 1/7/85 Program OI-13 Emergency Dose Assessmont Completed 1/7/85 Computer Model OI-14 Procedures Generation Package Partial Response 1/28/85 & 4/10/85 01-15 Human Factors Engineering Completed 4/10/85 M P8 5 27/10 1-mr
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2 R.
L.
Mittl to A.
Schwencer Item No.
Subject Status ltr. dated C-1 Feedwater Isolation Check Open Valve Analysis C-2 Plant-unique Analysis Report Completed 1/8/85 & 1/31/85 C-3 Inservice Testing of Pumps and Open Valves C-4 Fuel Assembly Accelerations Completed Amendment 8 C-5 Fuel Assembly Liftoff Completed Amendment 8 C-6 Review of Stress Report Open C-7 Use of Code Cases Completed 12/17/84 C-8 Reactor Vessel Studs and Partial Response 2/15/85 Fastners C-9 Containment Depressurization NRC Review Analysis C-10 Reactor Pressure Vessel Shield NRC Review Annulus Analysis C-ll Drywell Head Region Pressure NRC Review Response Analysis C-12 Drywell-to-Wetwell Vacuum NRC Review Breaker Loads C-13 Short-Term Feedwater System Open Analysis C-14 Loss-of-Coolant-Accident Completed 3/1/85 Analysis C-15 Balance-of-Plant Testability Completed Amendment 8 Analysis C-16 Instrumentation Setpoints Completed 2/15/85 C-17 Isolation Devices Open C-18 Regulatory Guide 1.75 NRC Review C-19 Reactor Mode Switch NRC Review C-20 Engineered Safety Features Open Reset Controls M P85 27/10 2-m r
m.
3 R.
L.
Mittl to 4
A.
Schwencer Item No.
Subject Status ltr. dated C-21 High Pressure Coolant Injection Open Initiation C-22 IE Bulletin 79-27 Completed Amendment 8 C-23 Bypassed and Inoperable Status NRC Review Indication C-24 Logic for Low Pressure Coolant Open Injection Interlock Circuitry C-25 End-of-Cycle Recirculation Pump Completed 3/1/85 Trip C-26 Multiple Control System Failures NRC Review C-27 Relief Function of Safety / Relief Completed 2/15/85 Valves C-28 Main Steam Tunnel Flooding Open Analysis C-29 Cable Tray Separation Testing Completed 4/4/85 C-30 Use of Inverter as Isolation Completed 3/7/85 Device C-31 Core Damage Estimate Procedure Open C-32 Continuous Airborne Particulate Open Monitors C-33 Qualifications of Senior Radiation Open l
Protection Engineer C-34 Onsite Instrument Information Open C-35 Airborne Iodine Concentration Open Instruments C-36 Emergency Plan Items Partial Response 11/9/84, 1/16/85, 2/7/85 &
i 4/4/85 o
C-37 TMI Item II.K.3.18 Partial Response 3/1/85 &
4/22/85 M P85 27/10 3-mr
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ATTACHMENT 2 ITEM NO.
SER SECTION SUBJECT C-37 15.9.3 TMI Item II.K.3.18 DJD:mr M P85 27/10 4-mr
ATTACHMENT 3 4
e CONFIRMATORY ITEM 37-(SER SECTION 15.9.3)
TMI ITEM II.K.3.18 The applicant has committed to modify the ADS logic to bypass the high drywell pressure trip after a sustained lower water level signal and to add a manual. switch that may be used to inhibit ADS actuation if necessary.
This is consistent with Option 4 of the BWROG study and is acceptable to the staff with the following conditions:
3)' The use of the inhibit switch must be addressed in the plant emergency procedures.
.The staff finds the conceptual design for ADS logic modifi-cations proposed by the applicant acceptable confirmatory on completion of the above specified actions.
RESPONSE
The use of the inhibit switch is addressed in plant operating procedures OP-EO.ZZ-101(O), " Reactor / Pressure Vessel (RPV) Control," and OP-EO.ZZ-201(O), " Level Restoration."
M P85 76/08 1-mw