ML20129J770
| ML20129J770 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 07/19/1985 |
| From: | Mittl R Public Service Enterprise Group |
| To: | Butler W Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8507230333 | |
| Download: ML20129J770 (12) | |
Text
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O PSEGET6' 80 Park Plaza, Newark, NJ 07101/ 201430-8217 MAILING ADDRESS / P.O. Box 570, Newark, NJ 07101 Robert L. Mitti General Manager Nuclear Assurance and Regulation July 19, 1985 Director of Nuclear Reactor Regulation U.S.
Nuclear Regulatory Commission 7920 Norfolk Avenue Bethesda, MD 20814 Attention:
Mr. Walter Butler, 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 1.7 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 12 of the HCGS FSAR.
Should you have any questions or require any additional information on these items, please contact us.
Very truly yours, h/,4 I
8507230333 850719 PDR ADOCK 05000354 E
PDR Y
Attachments
- g The Energy People 95431214M) 7 83
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l Director ' of Nuclear Reactor Regulation 2
7/19/85 C
'D.-H. Wagner USNRC Licensing Project Manager (w/ attach.)
.A.
R.' Blough
-USNRC Senior Resident Inspector (w/ attach.)
,s M P84 154/04 1/2 i
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Date:
7/19/85 ATTACHMENT 1 i
R.
L. Mittl to A.
Schwencer Item No.
Subject Status ltr. dated i*
~OI Riverborne Missiles
' Completed 1/31/85, 2/22/85, 5/8/85
,OI-2 Equipment Qualification Partial Response 2/1/85,.2/20/85, 2/28/85, 3/1/85, 6/11/85, 6/6/85, m
6/25/85-(2),
6/28/85,7/16/85 OI-3
~ Preservice Inspection. Program Partial Response 2/14/85 & 3/19/85
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OI-4' GDC 51 Compliance Completed 3/12/85
'OI-5 Solid-State Logic Modules Partial Response 6/5/85 I
'OI-6
.Postaccident Monitoring Completed 5/14/85
~
Instrumentation 1
LOI-7.
Minimum Separation'Between Partial Response 4/4/85 Non-Class IE Conduit and Class IE Cable Trays OI-8' l Control of. Heavy Loads Closed 1/18/85 (SSER 1)
JOI-9
' Alternate and Safe Shutdown NRC Action OI-10 Delivery of Diesel Generator Closed Amendment 8
' Fuel Oil and Lube Oil (SSER 1) -
-OI-ll' Filling of Key Management Open l
Positions-OI ' Training Program Items (a) -Initial-Training Program Completed 1/7/85-(b)' ~Requalification Training Completed 12/28/84, 4/26/85 Program (Revised Program)
(c)
Replacement Training:
Completed 1/7/85 Program (d)
TMI Issues I.A.2.1, Completed 1/7/85 r
I.A.3.1, and II.B.4
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(e)' Nonlicensed Training Completed 1/7/85 Program
^
OI-13 Emergency Dose Assessment Completed 1/7/85 Computer Model
^M P85-27/10 1-mr.
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Mittl to A. Schwencer Itcm No.
Subject Status ltr. dated OI-14 Procedures Generation Package Partial Response 1/28/85 & 4/10/85 01-15 Human Factors Engineering Partial Response 4/10/85
~C-1 Feedwater Isolation Check Open Valve Analysis C-2 Plant-unique Analysis Report Completed 1/8/85, 1/31/85 6/12/85 & 7/2/85 C-3 Inservice Testing of. Pumps and Completed 7/12/85 Valves C-4 Fuel Assembly Accelerations Completed Amendment 8 C-5 Fuel Assembly Liftoff Completed Amendment 8 C-6 Review of Stress Report Completed 7/19/85 C-7 Use of Code Cases Completed 12/17/84 C-8 Reactor Vessel Studs and Completed 5/24/85 Rev. 1 Pastners 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 Complete 4/22/85 Analysis C-14 Loss-of-Coolant-Accident Completed 3/1/85 & 6/12/85 Analysis C-15 Balance-of-Plant Testability Completed Amendment 8 Analysis C-16 Instrumentation Setpoints Partial Response 2/15/85
-C-17 Isolation Devices Open
- M P85 27/10 2-mr
4 3
R.
L. Mittl to A.
Schwencer Itcm No.
Subject Status ltr. dated C-18 Regulatory Guide 1.75 NRC Review C-19 Reactor Mode Switch NRC Review C-20 Engineered Safety Features Partial Response 7/19/85 Reset Controls C-21 High Pressure Coolant Injection Completed 7/1/85 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 Completed 5/24/85 Analysis C-29 Cable Tray separation Testing Completed 4/4/85 C-30
'Use of Inverter as Isolation Completed 3/7/85 Device j:
C-31 Core Damage Estimate Procedure Completed 6/24/85 C-32 Continuous Airborne Particulate Completed 7/1/85 Monitors C-33 Qualifications of Senior Radiation Open Protection Engineer C-34 Onsite Instrument Information Completed 7/1/85 C-35 Airborne Iodine Concentration Completed 6/18/85 Instruments.
M P85 27/10 3-mr
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4 R.
L. Mittl to A. Schwencer i
Itsm No.
Subject Status ltr. dated C-36' Emergency Plan Items Partial Response 11/9/84, 1/16/85, 2/7/85, 4/4/85
& 7/19/85 j
C-37 TMI Item II.K.3.18 Partial Response 3/1/85 &
4/22/85 d '
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- MP 85 27/10 4-mr L
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ATTACHMENT 2 ITEM NO.
SER SECTION SUBJECT C-6 5.2.1.1 Review of Stress Report C-20 7.3.2.6 Engineered safety features reset controls.
DJDamr M P85 27/10 5-mr
ATTACHMEN_T 3 M P85 27/10 6-mr l
SER CONFIRMATORY ISSUE 6 (5.2.1.1)
Review of stress report However, the staff requires the applicant to comply with Article NA-3260 of the 1971 Edition of Section III of the ASME Code.
This is a confirmatory item.
_RESPO_NSE_
Article-NA-3260 of the 1971 Edition of Section III of the ASME Code provides guidance on the review of stress reports.
A review was performed for all RCPB components and it has been determined that they are in compliance with the requirements of Article NA-3260.
SER CONFIRMATORY ISSUE 20 (7.3.2.6)
ENGINEERED SAFETY-FEATURES RESET CONTROLS The staff requires that the applicant submit the revised electrical schematic / elementary diagrams for all safety-related, equipment (both NSSS and BOP) that has been modified to prevent its reverting back to its normal (non-emergency) mode af ter an ESF reset.
The staff will confirm that the valves noted above remain in their emergency mode upon an ESF reset, therefore, conforming with the recommendation of IE Bulletin 80-06.
Additionally, the staff will require preoperational tests to demonstrate that all equipment remains in its emergency mode upon removal of the actuating signal and/or resetting of the various isolating or actuation signals.
This is a confirmatory item.
RESPONSE
FSAR Sections 14. 2.12.1. 4 5 a nd 14. 2.12.1. 4 7 have been revised to verify that all equipment remains in its emer-gency mode upon removal of the actuating signal and/or resetting of the various isolating or actuation signals.
The revised electrical schematic / elementary diagrams will be provided upon completion of the required modifications.
i JES:db MP85 139/06 1-db l
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2.
All logic combinations initiating automatic closure are verified.
4 3.
All auxiliary actions, including alarms, computer alarms, fan starts, and damper action are checked.
d.
Acceptance Criteria 1.
All containment isolation valves shall close automatically upon re.ceipt of their isolation signals.
I 2.
Valve closure times shall be within the requirements of Table 6.2-16.
3.
on remurl of asfauring a ag awl (ESS) Mc)lor* resa kiny of the osuhdson or Q ua DOA Sogno-l* S$ U@MEDf rem"in5 t
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AT1*a"lYrinY,Vanlunciators, instruments, and interlocks shall function in accordance with the system electrical schematics.
14.2.12.1.46 SP-Process Radiation Monitoring a.
Objective f
The test objective is to verify the capability of the process radiation monitoring system to detect radioactivity in the monitored process lines.
l b.
Prerequisites
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1.
All permanently installed equipment, relays, and l
instrumentation have been functionally operated and calibrated.
2.
Sections of the monitored systems required for the test are operational.
3.
Ac and de power as available.
14.2-107 Amendment 4 t
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j (c)
The de system loads respond and operate properly throu.ghout the test period.
d.
Acceptance Criteria 1.
On a loss of standby bus power, diesel generators start and load shed and sequence as specified in l
Table 8.3-1.
2.
On total loss of offsite power, diesel generators start, shed loads, and accept the sequenced loads as specified in Table 8.3-1.
3.
Integrated ECCS response demonstrates the ability of RHR and core spray to inject water into the reactor vessel at the flow rates and within the times specified in the GE Preoperational test specification.
4.
Integrated ECCS response in conjunction with simulated LOCA/LOSP signals demonstrates the ability of the diesel generators to maintain ECCS load while they provide rated flow to the vessel within the time specified in the GE preoperational test specification.
5.
Dc system loads operate at voltage levels which occur during integrated ECCS response to a simulated LOCA event in conjunction with LOSP and inoperable battery chargers.
on remo s I of-actuaHny.sogant ce^-w] and/or reseWay a f 'M e-k 1says t >ba or u.c.+u-a.+ ion sesna 1 eguipment remains in emeryancy 14.2.12.1.48 i'ueI" Handling and Vessel Servicing Equipment-a.
Objectives 1.
To verify all interlocks and logic associated with the refueling platform and service platform.
2.
To verify use of tools for servicing control rods, fuel assemblies, incore detectors.
14.2-112 Amendment 6
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