ML040230729

R. E. Ginna Nuclear Power Plant, Revised Technical Specification Pages 3.1.3-1, 3.1.3-2, 3.3.6-1, 3.3.6-2, 3.3.6-3, Attachments 1 and 2

ML040230729
Person / Time
Site:	Ginna
Issue date:	01/22/2004
From:	Clark R NRC/NRR/DLPM/LPD1
To:	Harris J NRC/OCIO/IRDMD/RMB
References
TAC MB1184
Download: ML040230729 (12)

Text

LICENSE AUTHORITY FILE CORRECTIONS TO LICENSE AND TECHNICAL SPECIFICATION PAGES BASED ON NRC STAFF REVIEW OF THE LICENSE AUTHORITY FILE FOR R.E. GINNA NUCLEAR POWER PLANT DOCKET NO. 50-244 Replace the following pages of Appendix A Technical Specifications with the attached revised pages.

Remove Insert Amendment/Correction Letter N/A 3.1.3-1 Amendment 80 N/A 3.1.3-2 Amendment 80 3.3.6-1 3.3.6-1 Amendment 83 3.3.6-2 3.3.6-2 Amendment 83 3.3.6-3 3.3.6-3 Amendment 83 Attachment 1

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 June 26, 2001 Dr. Robert C. Mecredy Vice President, Nuclear Operations Rochester Gas and Electric Corporation 89 East Avenue Rochester, NY 14649

SUBJECT:

R. E. GINNA NUCLEAR POWER PLANT - AMENDMENT RE: IMPROVED TECHNICAL SPECIFICATION FORMATING CHANGE AND REVISION TO 10 CFR 50.59 (TAC NO. MB1 184)

Dear Dr. Mecredy:

The Commission has issued the enclosed Amendment No. 80 to Facility Operating License No. DPR-1 8 for the R. E. Ginna Nuclear Power Plant. This amendment is in response to your application dated February .14, 2001.

The amendment makes minor revisions in the Ginna Station Improved Technical Specifications (ITS) format to allow for maintaining, viewing, and publishing them with a different software package. The amendment also includes a revision to ITS Section 5.5.13, 'Technical Specifications (TS) Bases Control Program," to provide consistency with the changes to 10 CFR 50.59 as published in the Federal Register (64 FR 53852) dated October 4, 1999.

A copy of the related Safety Evaluation is also enclosed. A Notice of Issuance will be included in the Commission's biweekly FederalRegister notice.

Sincerely,

/RAI Guy S. Vissing, Sr. Project Manager, Section 1 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-244

Enclosures:

1. Amendment No. 80 to License No. DPR-1 8

2. Safety Evaluation cc w/encds: See next page

MTC 3.1.3 3.1 REACTIVITY CONTROL SYSTEMS 3.1.3 Moderator Temperature Coefficient (MTC)

LCO 3.1.3 The MTC shall be maintained within the limits specified in the COLR.

The maximum upper limit shall be less than or equal to 5 pcm/OF for power levels below 70% RTP and less than or equal to 0 pcm/PF at or above 70% RTP.

APPLICABILITY: MODE 1 and MODE 2 with keff 2 1.0 for the upper MTC limit, MODES 1, 2, and 3 for the lower MTC limit.

ACTIONS CONDITION REQUIRED ACTION l_COMPLETION TIME A. MTC not within upper A.1 Establish administrative 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> limit. withdrawal limits for control banks to maintain MTC within limit.

B. Required Action and B.1 Be in MODE 2 with keff 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion < 1.0.

Time of Condition A not met.

C. - NOTE -

- NOTE - LCO 3.0.4 is not applicable.

Required Action C.1 must be completed whenever C.1 Re-evaluate core design Once prior to Condition C is entered. and safety analysis, and reaching the determine that the reactor equivalent of an Projected end of cycle life core is acceptable for equilibrium RTP all (EOL) MTC not within continued operation. rods out (ARO) lower limit. boron concentration of 300 ppm D. Required Action and D.1 Be in MODE 4. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> associated Completion Time of Condition C not met.

R.E. Ginna Nuclear Power Plant 3.1 .3-1 Amendment 80

MTC 3.1.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.3.1 Verify MTC is within upper limit. Once prior to entering MODE 1 after each refueling SR 3.1.3.2 Confirm that MTC will be within limits at 70% RTP. Once prior to entering MODE 1 after each refueling SR 3.1.3.3 Confirm that MTC will be within limits at EOL. Once prior to entering MODE 1 after each refueling.

R.E. Ginna Nuclear Power Plant 3.1 .3-2 Amendment 80

-7,%o UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 August 29, 2003 Dr. Robert C. Mecredy Vice President, Nuclear Operations Rochester Gas and Electric Corporation 89 East Avenue Rochester, NY 14649

SUBJECT:

R. E. GINNA NUCLEAR POWER PLANT - AMENDMENT RE: CONTROL ROOM EMERGENCY AIR TREATMENT SYSTEM ACTUATION INSTRUMENTATION CHANGE (TAC NO. MB11887)

Dear Dr. Mecredy:

The Commission has issued the enclosed Amendment No. 83 to Facility Operating License No.

DPR-1 8 for the R. E. Ginna Nuclear Power Plant. This amendment is in response to your application dated May 3, 2001, as supplemented August 7, 2001, October 29, 2001, May 3, 2002, October 7, 2002, November 5, 2002 and June 6, 2003.

The amendment revises the Improved Technical Specifications to reflect design changes to the actuation circuitry associated with the Control Room Emergency Air Treatment System. The proposed design changes consist of replacing the current radiation monitors with two Geiger-Mueller tubes powered from two independent safety-related power supplies which are then configured into two redundant actuation logic trains. The actuation logic trains utilize safety-grade digital instrumentation which meet Class 1E safety system requirements.

A copy of the related Safety Evaluation is also enclosed. A Notice of Issuance will be included in the Commission's biweekly Federal Register notice.

Sincerely, IRA/

Robert Clark, Project Manager, Section 1 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-244

Enclosures:

1. Amendment No. 83 to License No. DPR-1 8

2. Safety Evaluation cc w/encls: See next page

CREATS Actuation Instrumentation 3.3.6 3.3 INSTRUMENTATION 3.3.6 Control Room Emergency Air Treatment System (CREATS) Actuation Instrumentation LCO 3.3.E3 The CREATS actuation instrumentation for each Function in Table 3.3.6-1 shall be OPERABLE.

APPLICABILITY: MODES 1, 2, 3, and 4, During movement of irradiated fuel assemblies, During CORE ALTERATIONS.

ACTIONS

-NOTE-Separate Condition entry is allowed for each Function.

CONDITION REQUIRED ACTION l COMPLETION TIME A. One or more Functions A.1 I with one channel or train ------------------

inoperable. - NOTE-The control room may be unisolated for < 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> while in this condition.

Place CREATS in Mode F. 7 days B. One or more Functions B.1 with two channels or two ------------------

trains inoperable. - NOTE -

The control room may be unisolated for < 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> while in this condition.

I Place CREATS in Mode F. Immediately C. Required Action and C.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> I associated Completion Time of Condition A or B AND I not met in MODE 1, 2, 3, or 4. C.2 Be in MODE 5. 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> R.E. Ginna Nuclear Power Plant 3.3.6-1 Amendment 83

CREATS Actuation Instrumentation 3.3.6 CONDITION REQUIRED ACTION COMPLETION TIME I D. Required Action and D.1 Suspend CORE Immediately associated Completion ALTERATIONS.

I Time of Condition A or B not met during movement AND of irradiated fuel I

assemblies or during D.2 Suspend movement of Immediately CORE ALTERATIONS. irradiated fuel assemblies.

SURVEILLANCE REQUIREMENTS

-NOTE-Refer to Table 3.3.6-1 to determine which SRs apply for each CREATS Actuation Function.

SURVEILLANCE FREQUENCY SR 3.3.6.1 Perform CHANNEL CHECK. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> SR 3.3.6.2 Perform COT. 92 days SR 3.3.6.3 - NOT-E-Verification of setpoint is not required.

Perform TADOT. 24 months SR 3.3.6.4 Perform CHANNEL CALIBRATION. 24 months SR 3.3.6.5 Perform ACTUATION LOGIC TEST. 24 months R.E. Ginna Nuclear Power Plant 3.3.6-2 Amendment 83

CREATS Actuation Instrumentation 3.3.6 Table 3.3.6-1 CREATS Actuation Instrumentation REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CHANNELS REQUIREMENTS VALUE

1. Manual Initiation 2 trains SR 3.3.6.3 NA

2. Automatic Actuation Logic and Actuation Relays 2 trains SR 3.3.6.5 NA

3. Control Room Radiation Intake Monitors 2 SR 3.3.6.1 * .5 mR/hr SR 3.3.6.2 SR 3.3.6.4 R.E. Ginna Nuclear Power Plant 3.3.6-3 Amendment 83

NRR FILE CORRECTIONS TO LICENSE AND TECHNICAL SPECIFICATION PAGES BASED ON NRC STAFF REVIEW OF THE LICENSE AUTHORITY FILE FOR R.E. GINNA NUCLEAR POWER PLANT DOCKET NO. 50-244 Replace the following pages of Appendix A Technical Specifications with the attached revised pages.

Remove Insert Amendment/Correction Letter N/A 3.1.3-1 Amendment 80 N/A 3.1.3-2 Amendment 80 Attachment 2

-0>o UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 a*+

June 26, 2001 Dr. Robert C. Mecredy Vice President, Nuclear Operations Rochester Gas and Electric Corporation 89 East Avenue Rochester, NY 14649

SUBJECT:

R. E. GINNA NUCLEAR POWER PLANT - AMENDMENT RE: IMPROVED TECHNICAL SPECIFICATION FORMATING CHANGE AND REVISION TO 10 CFR 50.59 (TAC NO. MB1 184)

Dear Dr. Mecredy:

The Commission has issued the enclosed Amendment No. 80 to Facility Operating License No. DPR-1 8 for the R. E. Ginna Nuclear Power Plant. This amendment is in response to your application dated February 14, 2001.

The amendment makes minor revisions in the Ginna Station Improved Technical Specifications (ITS) format to allow for maintaining, viewing, and publishing them with a different software package. The amendment also includes a revision to ITS Section 5.5.13, 'Technical Specifications (TS) Bases Control Program," to provide consistency with the changes to 10 CFR 50.59 as published in the Federal Register (64 FR 53852) dated October 4, 1999..

A copy of the related Safety Evaluation is also enclosed. A Notice of Issuance will be included in the Commission's biweekly Federal Register notice.

Sincerely,

/RAI Guy S. Vissing, Sr. Project Manager, Section 1 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-244

Enclosures:

1. Amendment No. 80 to License No. DPR-1 8

2. Safety Evaluation cc w/encds: See next page

MTC 3.1.3 3.1 REACTIVITY CONTROL SYSTEMS 3.1.3 Moderator Temperature Coefficient (MTC)

LCO 3.1.3 3 The MTC shall be maintained within the limits specified in the COLR.

The maximum upper limit shall be less than or equal to 5 pcm/OF for power levels below 70% RTP and less than or equal to 0 pcm/0 F at or above 70% RTP.

APPLICABILITY: MODE 1 and MODE 2 with keff 2 1.0 for the upper MTC limit, MODES 1, 2, and 3 for the lower MTC limit.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. MTC not within upper A.1 Establish administrative 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> limit. withdrawal limits for control banks to maintain MTC within limit.

B. Required Action and B.1 Be in MODE 2 with keff 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion < 1.0.

Time of Condition A not met.

- NOTE -

- NOTE - LCO 3.0.4 is not applicable.

Required Action C.1 must be completed whenever C.1 Re-evaluate core design Once prior to Condition C is entered. and safety analysis, and reaching the

_-_ _ _ __ _ __ _ _ _ __ _ _ .determine that the reactor equivalent of an core is acceptable for equilibrium RTP all Projected end of cycle life continued operation. rods out (ARO) weOL)limitC notwithiboron concentration lower limit. of 300 ppm D. Required Action and D.1 Be in MODE 4. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> associated Completion Time of Condition C not met.

R.E. Ginna Nuclear Power Plant 3.1 .3-1 Amendment 80

MTC 3.1.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.3.1 Verify MTC is within upper limit. Once prior to entering MODE 1 after each refueling SR 3.1.3.2 Confirm that MTC will be within limits at 70% RTP. Once prior to entering MODE 1 after each refueling SR 3.1.3.3 Confirm that MTC will be within limits at EOL. Once prior to entering MODE 1 after each refueling.

R.E. Ginna Nuclear Power Plant 3.1 .3-2 Amendment 80