ML20132C272
| ML20132C272 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 07/24/1985 |
| From: | Carey J DUQUESNE LIGHT CO. |
| To: | Eisenhut D Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737 2NRC-5-107, GL-82-33, NUDOCS 8507300092 | |
| Download: ML20132C272 (5) | |
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'Af 2NRC-5-107 (412) 787-5141 (412) 923-1960 Nuclear Construction Division Telecopy (412) 787-2629 Robinson Plaza, Building 2. Suite 210 Pittsburgh, PA 15205 7-24-85 United States Nuclear Regulatory Commission Washington, DC 20555 ATTENTION:
Mr. Darrell G. Eisenhut, Director Division of Licensing Office of Nuclear Reactor Regulation
SUBJECT:
Beaver Valley Power Station - Unit No. 2 Docket No. 50-412 Generic Letter 82-33 Supplement 1 to NUREG 0737, Revised Schedule Gentlemen:
Beaver Valley Power Station Unit 2 (BVPS-2) provided its res pons e to Generic Letter 82-33, Supplement 1 to NUREG 0737, on April 15, L983, via 2NRC-3-017.
Since that time Duquesne Light Company has revised its construc-tion schedule, and this change affects the previously submitted res po ns e.
Therefore, please find attached an updated Description for the BVPS-2 imple-mentation of the Supplement I to NUREG 0737.
DUQUESNE LIGHT COMPANY By
/
JvQ/ Carey Vice President MAH/wjs Attachment Mr. B. K. Singh, Project Manager (w/a) cc:
Mr. G. Walton, NRC Resident inspector (w/a)
INPO Records Center (w/a)
SUBSCRIBED AND$ WOP.N TO BEFORE ME THIS
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0724 Notary Public 73 g h [$oo g 2
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$H!PPthCP00100ee. NAvf 8 COUSIf Wf CONut1580s (IPtet$ $(PT.18,1935 Member, Pennsylvanie Assetistion of Noteries
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' United States Nuclesr Regulatory Commission Mr. Darrell G. Eisenhut, Director Generic Letter 82-33 Page 2 COMMONWEALTH OF PENNSYLVANIA )
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COUNTY OF BEAVER
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On this M day of
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/[/[G, before me, a said Co[monweaNh and County, personally appeared Notary Public in and for J.
J.
Carey, who being duly sworn, deposed and said that (1) he is Vice Pres ident of Duquesne Light, (2) he is duly authorized to execute and file the foregoing Submittal on behalf of said Company, and (3) the statements set forth in the Submittal are true and correct to the best of his knowledge.
CW&
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Notary Public iMilLA M. FAli0tt 110TA8V PUGUC SHIPPleGPeti 80e0. SEAvia COUNTY MY C0ede35604 EXPlat$ SEPT.16.1985 Member, Pennsylvene Associate of Noteries
Generic Letter 82-33, Supplement to NUREG 0737 Revised Schedule DESCRIPTIONS and SCHEDULES 2.1 Safety Parameter Display System 2.1.1 Schedule and Current Status The Safety Parameter Display System (SPDS) will operate from the Emergency Response Facilities Computer System (ERFCS).
An orde r was placed for the hardware and sof tware fo r both the ERFCS and the SPDS. An SPDS implementation plan and the safety analysis which describes the basis for parameter selection was submitted. The SPDS will be available for operator training by November 30, 1986, and operational three months prior to fuel load.
Operator training will be completed one month prior to fuel load. DLC does not desire a pre-implementation review.
2.1.2 NRC Review The three NRC review tasks, along with their schedules for completion, are listed below:
- Implementation Plan Submitted to NRC:
8/1/84 NRC review scheduled:
10/1/84 NRC review actual:
not yet received
- Safety Analysis Report Submitted to NRC:
7/31/84 NRC review scheduled:
10/1/84 NRC review actual:
not yet received
- Post-Implementation Review NRC start review:
three months prior to fuel load NRC complete review:
one month prior to fuel load NRC issue SER:
one month prior to fuel load 2.1.3 Integration with Other Activities The SPDS for BVPS-2 is being planned for completion and instal-lation unrestrained by progress in any of the other four activ-itles per Generic Letter 82-33.
The various design documents developed for the SPDS will serve as inputs to other act iv it ie s.
r-2.2 Detailed Control Room Design Review 2.2.l Schedule and Current Status Resources required to conduct the Detailed Control Room Design Review and technical requi reme nt s have been allocated.
The DCRDR Program Plan was submitted on August 8, 1983.
The DCRDR summary report will be submitted by December 30, 1985.
2.2.2 NRC Review Two reviews are required by the NRC:
- Program Plan Submitted to NRC:
8/8/83 NRC review scheduled:
11/1/83 NRC review actual:
1/23/84
- Summary Report Submit to NRC:
12/1/85 NRC review complete:
2/1/86 NRC issue SER:
2/1/86 2.3 Regulatory Guide 1.97 Instrumentation 2.3.1 Schedule and Current Status The report and summary tab les describing impleme nt at ion of Regulatory Guide 1.97 are contained in the BVPS-2 FSAR, Section 7.5.
To date, 56 purchase orders have been approved for Cate-gory L instruments out of a total 72.
Ins t rument at ion listed in the t ab le s is expect ed to be installed and operational by fuel load date.
2.3.2 NRC Review There is one review required by the NRC:
- Implementation Plan Submitted to NRC:
9/12/83 NRC review scheduled:
11/15/83 NRC review actual:
5/2/85 2.3.3 Integration with Other Activities Engineering studies using Regulatory Guide 1.97 (Rev. 2) were performed and completed to suppo rt preparation of BVPS-2 Final Safety Analysis Report, Section 7.5.
These studies and the engineu ring and design information derived f r om them, will be used as information inputs to the other four activities.
2.4 Emergency Operating Procedures Upgrade 2.4.1 Schedule and Current Status Westinghouse Owners Group generic technical guidelines are the basis for BVPS-2 E0P's.
They have been submitted to the NRC.
The procedures generation package has been submitted. Operators will be licensed using upgraded E0P's.
2.4.2 NRC Review The NRC review tasks, along with their schedules fo r comple-tion, are shown below:
- BVPS-2 Procedures Generation Package Submitted to NRC:
7/26/84 NRC review scheduled:
10/1/84 NRC review actual:
not yet completed 2.4.3 Integration with,pther Activities Upgraded E0P's, developed from the Westinghouse Owner's Group generic Emergency Response Guidelines, will use plant info rma-t ion identified in the Regulatory Guide 1.97 engineering s.tud ies.
Initially, the E0P's will be developed without the operation of the SPDS.
When the SPDS software manuals become available, they will be reviewed for pos sible incorporation into the E0P's, 2.5 Emergency Response Facilities 2.5.1 Schedule and Current Status The ERF's that support operation of BVPS-2 are shared facili-ties designated as site ERF's.
Refer to DLC's submittal fo r BVPS-1 for details of ERF construction.
Structure, procedur es,
and staff training actions will be completed in time fo r the BVPS-2 site drill.
Since the ERF computer system and SPDS will not be available until three months prior to fuel load, NRC assessment of these act ivit ies should be pe r fo rmed in two phases.
2.5.2 NRC Review The quality of ERF installation will be appraised by the NRC.
Actions concerning structure, procedures, and staff training will be completed prior to the BVPS-2 site dellt.
The NRC appraising these aspects of the ERF's during should plan on this situ drill.
The instrumentation systems for the TSC and EOF will be installed and operational by fuel load date.
The NRC will be pe r fo rming site audits during the time pe riods indicated.
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