ML17251B076: Difference between revisions

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===RESPONSE===
===RESPONSE===
Reference 2 states that the RVLIS was installed in March 1986. Reference 3 states that the RVLIS would be implemented into 'the Ginna Emergency Operating Procedures (EOPs) by the end of July 1987.                            These actions were completed.            To accomplish this, functional testing and calibration were completed prior to implementation.                            These results          are retained in the Ginna Station Central Records permanent file, EWR 2799 System Modifications (SM file), and are available for          NRC          inspection.
Reference 2 states that the RVLIS was installed in March 1986. Reference 3 states that the RVLIS would be implemented into 'the Ginna Emergency Operating Procedures (EOPs) by the end of July 1987.                            These actions were completed.            To accomplish this, functional testing and calibration were completed prior to implementation.                            These results          are retained in the Ginna Station Central Records permanent file, EWR 2799 System Modifications (SM file), and are available for          NRC          inspection.
8805130065 880503
8805130065 880503 PDR RDOCK 05000244                  DCD P
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PDR RDOCK 05000244                  DCD P


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Revision as of 11:22, 4 February 2020

Submits Addl Info Re Implementation Rept on Reactor Vessel Level Indication Sys
ML17251B076
Person / Time
Site: Ginna 
Issue date: 05/03/1988
From: Snow B
ROCHESTER GAS & ELECTRIC CORP.
To: Stahle C
NRC, NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
NUDOCS 8805130065
Download: ML17251B076 (11)


Text

I

'ACCELERATED DISIBUTION DEMONSTRATION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:8805130065 DOC.DATE: 88/05/03 NOTARIZED: NO DOCKET FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G 05000244 AUTH. NAME AUTHOR AFFILIATION SNOW,B.A. Rochester Gas 6 Electric Corp.

RECIP.NAME RECIPIENT AFFILIATION STAHLE,C. Document Control Branch (Document Control Desk)

SUBJECT:

Provides addi info re implementation rept on reactor vessel level indication sys.

DISTRIBUTION CODE: AOOID TITLE: OR COPIES RECEIVED:LTR Submittal: General Distribution

'I ENCL 3 SIZE:

NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72). 05000244 ~

I l I 'II I

RECIPIENT COPIES RECIPIENT 'OPIES'D ID CODE/NAME LTTR ENCL CODE/NAME LTTR ENCL PD1-3 LA 1 0 PD1-3 PD 5 5 STAHLE, C 1 1' ARM/DAF/LFMB 1 0 NRR/DEST/ADS 7E 1 1 A'NTERNAL:

NRR/DEST/CEB 8H 1 1 NRR/DEST/ESB 8D 1 1 NRR/DEST/MTB 9H 1 1 NRR/DEST/RSB 8E 1 1 NRR/DOEA/TSB 11 1 1 NRR/PMAS/ILRB12 1 1 NUDOCS-ABSTRACT 1 1 OGC 15-B-18 1 0 01 1 1 RES/DE/EIB 1 1 EXTERNAL: LPDR 1 1 NRC PDR 1 1 NSIC 1 1 R,

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'A TOTAL NUMBER OF COPIES REQUIRED: LTTR 22 ENCL 19

0

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YORK

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$ 1a'lt ROCHESTER GAS AND ELECTRIC CORPORATION o 89 EAST AVENUE, ROCHESTER, N.K 14649-0001 TELEPHONC ARE* cooK 7I5 546.2700 May 3, 1988 U.S. Nuclear Regulatory Commission Document Control Desk Attn: Mr. Carl Stahle PWR Project Directorate No.

washington, D.C. 20555

Subject:

Additional Information Implementation Report Reactor Vessel Level Indication System R.E. Ginna Nuclear Power Plant Docket No. 50-244

Dear Mr. Stahle:

In accordance with the "Implementation Letter Report Content" format requested in Enclosure 2 to the NRC's June 4, 1984 letter on this subject, the following additional information concerning our Reference 1 submittal is being supplied. Reference 1 describes the Reactor Vessel Level Indication System (RVLIS) installed at Ginna.

NRC REQUEST:

(1) Provide notification that the system installation, functional testing, and calibration is complete and test results are available for inspection.

RESPONSE

Reference 2 states that the RVLIS was installed in March 1986. Reference 3 states that the RVLIS would be implemented into 'the Ginna Emergency Operating Procedures (EOPs) by the end of July 1987. These actions were completed. To accomplish this, functional testing and calibration were completed prior to implementation. These results are retained in the Ginna Station Central Records permanent file, EWR 2799 System Modifications (SM file), and are available for NRC inspection.

8805130065 880503 PDR RDOCK 05000244 DCD P

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NRC REQUEST=

(2) Summary of licensee conclusions based on test results, e.g.:

(a) the system performs in accordance with design expectations and within design error tolerances; or (b) description of deviations from design performance specifications and basis for concluding that the deviations are acceptable.

RESPONSE=

The RVLIS was installed in March 1986. As described. in Reference apparent 2, during the implementation process that the analytically estimated worst case it became uncertainties were larger than judged acceptable for use in detection and mitigation of degraded core cooling.

Therefore, the system was modified to the RVLIS described in Reference 1 which is currently installed. This modified RVLIS performs in accordance with the design expectations and design error tolerances noted in Attachments A and B to RGGE's September 18, 1987 submittal.

NRC REQUEST:

(3) Description of any deviations of the as-built syst: em from previous design descriptions with any appropriate explanation.

RESPONSE=

The as-built RVLIS installed at Ginna conforms to the description presented in Reference 1.

NRC REQUEST:

(4) Request for modification of Technical Specifications to include all ICC instrumentation for accident monitoring.

RESPONSE

A Technical Specification Amendment for the RVLIS has been submitted by Reference 5.

NRC REOUEST-(5) Request, for NRC approval of the plant-specific installation.

RESPONSE=

The NRC is requested to approve the RVLIS described in Reference 1.

NRC REQUEST=

(6) Confirm that the EOPs used for operator training will conform to the technical content of NRC approved EOP guidelines (generic or plant specific).

RESPONSE

The EOPs for RVLIS implementation used at Ginna conform to the Westinghouse Owners Group Emergency Response Guidelines, Rev. 1. The Ginna specific procedures were developed using these guidelines. The process used for procedure development was described in the Ginna Procedure Generation Package submitted to the NRC by letter dated February 28, 1985.

Very truly yours,

~7 ruce A. Snow Superintendent Nuclear Production

Attachment:

List of References

LIST OF REFERENCES RG&E to NRC letter dated September 18, 1987 from R.W.

Kober to C. Stahle, "Inadeauate Core Cooling Instrumentation" RG&E to NRC letter dated March 18, 1987 from R.W. Kober to G.E. Lear, "Inadeauate Core Cooling Xnstrumentation Implementation Schedule Revision" RG&E to NRC letter dated June 11, 1987 from R.W. Kober to C. Stahle, "Inadeauate Core Cooling Xnstrumentation Implementation Environmental Qualification Stipulation" RG&E to NRC letter dated December 22, 1986 from R.W.

Kober to G.E. Lear, "Xmplementation Report Reactor Vessel Level Indication System" RG&E to NRC letter dated September 24, 1987 from R.W.

Kober to C. Stahle, Submittal for RVLIS Technical Specification Amendment

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Dist:

Docket 50-244 PD I-3 Reading

(

2 1S88 MgiY C. Stahle M. Rushbrook DOCKET NO(S). 50-244 Hr. Roger M. Kober, Vice President Electric and Steam Production Rochester Gas 8 Electric Corporation 89 East Avenue Rochester, Hew York 14649

SUBJECT:

R. E. Ginna Nuclear Power Plant The following documents concerning our review of the subject facility are transmitted for your information.

Notice of Receipt of Application, dated Draft/Final Environmental Statement, dated Q Notice of Availability of Draft/Final Environmental Statement, dated Safety Evaluation Report, or Supplement No. dated Environmental Assessment and Finding of No Significant Impact, dated Notice of Consideration of Issuance of Facility Operating License or Amendment to Faci 1 i ty Operating Li cense, dated tkj Hi-Weekly

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  • d id )'d Notice; Applications and Amendments to Operating Licenses Involving No d))))))) ) )))

Exemption, dated Construction Permit No. CPPR- , Amendment No. dated Facility Operating License No. , Amendment No. dated Order Extending Construction Completion Date, dated Monthly Operating Report for transmitted by letter dated Annual/Semi-Annual Report-transmitted by letter dated Office of Nuclear Reactor Regulation

Enclosures:

As stated with enclosure See attached sheet OFFlCEP gRPP ~ 0 A ~ ~ ~ ~ ~ ~ ~ ~ ~ I~~

sURNAMEy MRushbr 1)

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~~~ ~ ~

oAvE1 A~ 5/2/

NRC FORM 3ls IIOIBOl HRCM 0240 OFFICIAL RECORD COPY

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Mr. Roger W. Kober Rochester Gas and Electric Corporation R. E. Ginna Nuclear Power Plant CC:

Harry H. Voigt, Esquire Mr. Bruce A. Snow, Superientendent LeBoeuf, Lamb, Leiby and MacRae Nuclear Production 1333 New Hampshire Avenue, N.W. Rochester Gas 5 Electric Corporation Suite 1100 89 East Avenue Washin'gton, D.C. 20036 Rochester, N.Y. 14649-0001 Ezra Bialik Assistant Attorney General Environmental Protection Bureau New York State Department of Law 2 World Trade Center New York, New York 10047 Resident Inspectnr R.E. Ginna Plant c/o U.S. NRC 1503 Lake Road Ontario, New York 14519 Stanley B. Klimberg, Esquire General Counsel New York State Energy Office Agency Building 2 Empire State Plaza Albany, New York 12223 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King o< Prussia, Pennsylvania 19406 Supervisor of the Town of Ontario 1850 Ridge Road Ontario, New York 14519 Ms. Donna Ross Division of Policy Analysis A Planning New York State Energy Office Agency Building 2 Empire State Plaza Albany, New York 12223,