ML17309A594

Provides PTLR & Methodology Used for Future Changes to PTLR for Plant

ML17309A594
Person / Time
Site:	Ginna
Issue date:	12/08/1995
From:	Mecredy R ROCHESTER GAS & ELECTRIC CORP.
To:	Andrea Johnson NRC (Affiliation Not Assigned), NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML17264A280	List: ML17264A279 ML17264A281 ML17309A594
References
NUDOCS 9512120153
Download: ML17309A594 (5)

Text

4ND ROCHESTER GAS AND ELECI1C CORRORAVON ~ 89EASTAVENUE, ROCHESlER, N. Y 14649-0001 AREA CODE716 5'-2700 ROBERT C. MECREDY Vice President Nuclear Operotions December 8, 1995 U.S. Nuclear Regulatory Commission Document Control Desk Attn: Allen R. Johnson Project Directorate I-1 Washington, D.C. 20555

Subject:

Technical Specification Improvement Program, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR)

R.E. Ginna Nuclear Power Plant Docket No. 50-244

Dear Hr. Johnson,

The purpose of this letter is to provide the PTLR, and the methodology used .for future changes to the PTLR for Ginna Station. As such, this submittal supersedes, the PTLR methodology provided in Reference (a) and the PTLR provided in Reference (b).

Attachment I contains the proposed PTLR for Ginna Station. This PTLR includes all changes requested by the NRC staff during several conference calls conducted between RG&E and the NRC in September, October, and November 1995. The PTLR contains the same heatup and cooldown curves and the low temperature overpressurization (LTOP) system setpoints as current Ginna Station Technical

~

Specifications 3. 1.2. 1 and 3. 15. 1, respectively. The minimum requirements of the PTLR as specified in Table 1 of Reference (c) is summarized in. Table 1 to this submittal.

The methodology for establishing future changes to the current RCS pressure and temperature limits for heatup, cooldown, criticality, and hydrostatic testing, as well as heatup and cooldown rates will be in accordance with WCAP-14040, Revision 1 as approved by the NRC by Reference (c). The only exception to this is'that RG&E will use ENDF/B-IV for dosimetry calculations instead of ENDF/B-VI as proposed by the NRC staff.

The NRC's approval of this methodology requested that implementing licensees address the three topics below:

a. Reactor vessel plant-specific surveillance program;

b. Use of plant-specific surveillance data in calculating adjusted reference temperatures; and c ~ Use of RHR relief valves as part of the cold overpressure mitigation system.

Items a and b are discussed in the PTLR provided in Attachment I while item c is addressed in the discussion of the RG&E specific LTOP System setpoint methodology provided in Attachment II.

Future changes to the power operated relief valve (PORV) lift settings required for the LTOP System and the LTOP enable temperature will be in accordance with the methodology provided in Attachment II to this letter. This methodology replaces Section 3.0 of WCAP-14040, Revision 1 and contains all changes requested by the NRC staff as documented in Reference (d) and discussed during a conference call on October 18, 1995. Included within Attachment II are two copies of the LTOP methodology. The first copy contains a retyped version of the LTOP methodology. The second copy is a "redlined" version of the methodology showing all differences between this submittal and that provided in Reference (a).

RG&E believes that this closes all issues related to the proposed PTLR for Ginna Station. Please contact Mark Flaherty at (716) 724-8512 if you have any further questions related to this issue.

Very uly yours, Robert C. Hecred

References:

(a) Letter from R.C. Hecredy, RG&E, to A.R. Johnson, NRC,

Subject:

Technical Specification Improvement Program, dated Hay 5, 1995.

(b) Letter from R.C. Hecredy, RG&E, to A.R. Johnson, NRC,

Subject:

Application for Amendment to Facility Operating License, Conversion to Improved Technical Specifications, dated Hay 26, 1995 (Attachment G).

(c) Letter from C. I. Grimes, NRC, to R.A. Newton, WOG,

Subject:

Acceptance for Referencing of Topical Report h!CAP-14040, Revision 1, "Hethodology Used to Develop Cold Overpressure Nitigating System Setpoints and RCS Heatup and Cooldown Limit Curves (TAC ¹891749), dated October 16, 1995.

(d) Letter from R.C. Hecredy, RG&E, to A.R. Johnson, NRC,

Subject:

Technical Specification Improvement Program, Reactor Coolant System (RCS) Pressure and Temperature Limits Report, dated July 17, 1995.

HDFKPTLR xc: U.S. Nuclear Regulatory Commission Hr. Allen R. Johnson (Mail Stop 14B2)

PWR Dir ectorate I-l Washington, D.C. 20555 U.S. Nuclear Regulatory Commission Hs. Haggalean Weston (Mail Stop -.011E22)

Technical Specifications Branch Washington, D.C. 20555 U.S. Nuclear Regulatory Commission Hr. Carl Schulten (Hail Stop 011E22) w/o attachments Technical Specifications Branch Washington, D.C. 20555 U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 .

Ginna Senior Resident Inspector

Table 1 - PTLR Contents Minimum Requirements To Be Included in Location in PTLR PTLR Provide the values of neutron fluences Table 5 that are used in the adjusted reference temperature (ART) calculation.

Provide the surveillance capsule Table 1 provides the withdrawal schedule, or reference by title withdrawal schedule.

and number the documents where the Table 6, Note (b) schedule is located. Also, reference the reference the listing surveillance capsule reports by title and of surveillance capsule number if ARTS are calculated using reports.

surveillance data.

Provide the LTOP setpoint curves or Section 2.2 and 2.3 setpoint values.

Identify both the limiting ART values and Table 6 provide the limiting materials at the 1/4T and 3/4T limiting ART values.

locations (T - vessel beltline thickness). Section 4. 1 provides Also, identify RT~8 value in accordance the RTpy8 value.

with 10 CFR 50.61.

Provide the P/T curves for heatup, Figures 1 and 2 cooldown, criticality, and hydrostatic and leak tests.

Identify minimum temperatures on the P/T Figures 1 and 2, curves such as minimum boltup temperature Section 2.1.3 and hydrotest temperature.

Provide supplemental data and calculations Tables 2, 3, and 6 and of the chemistry factor in the PTLR if the Section 3.0 surveillance data are used in the ART calculation. Also, evaluate the surveillance data to determine if they meet the credibility criteria in Regulatory Guide 1.99, Revision 2 and provide the results.

Attachment I PTLR for Ginna Station