ML17264B067

Proposed Tech Specs,Correcting & Clarifying Info Re RCS Pressure & Temp Limits Rept Administrative Controls Requirements

ML17264B067
Person / Time
Site:	Ginna
Issue date:	10/08/1997
From:	ROCHESTER GAS & ELECTRIC CORP.
To:
Shared Package
ML17264B066	List: ML17264B065 ML17264B067
References
NUDOCS 9710150247
Download: ML17264B067 (10)

Text

e Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.6 PTLR (continued) c ~ The analytical methods used to determine the RCS pressure and temperature and LTOP limits shall be those previously reviewed and approved by the NRC in NRC letter dated <NRC approval document>. Specifically, the methodology is described in the following documents:

1. Letter from R.C. Hecredy, Rochester Gas and Electric Corporation (RG&E), to Document Control Desk, NRC, Attention: Guy S. Vissing, "Application for Facility Operating License, Revision to Reactor, Coolant System (RCS) Pressure and Temperature Limits Report (PTLR)

Administrative Controls Requirements," Attachment VI, September 29, 1997, as supplemented by letter from R.C. Hecredy, RG&E, to Guy S. Vissing, NRC, "Corrections to Proposed Low Temperature Overpressure Protection System Technical Specification," October 8, 1997.

2. WCAP-14040-NP-A, "Hethodology Used to Develop Cold Overpressure Hitigating System Setpoints and RCS Heatup and Cooldown Limit Curves," Sections 1 and 2, January, 1996.

d. The PiTLR shall be provided to the NRC upon issuance for each reactor vessel fluence period and for revisions or supplement thereto.

R..E. Ginna Nuclear Power Plant, 5.0-22 Amendment No. g, PP 97l0%50247 97l008 PDR ADOCK:05000244 P PDR

Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.6 PTLR (continued)

C. The SohTjt5i'algeet~83os'.'".'undid,'.:::;f o.,:detep.ije,':~t,e: RC pressure and temp'erature and LTOP liiiiits skale1 be thnose previously reviewed and approved by, the NRC.

in NRC letter dated Nay R!IT-II$6~(NRCyiappto:.vaI::-::.".:::::;do'clument>:. Specifically, the I1eIihe

+ad-methodology ~<i's described in the following documents:

1. Letter from A<<

Facility ti:

R.C. Mecredy, Rochester Corporation (RGKE), to Document Control Desk,

~'CW@igi:,,,::,i,--g, Gas and "Appl Operating License, Revision to Reactor Coolant System (RCS) Pressure and Temperature Limits Report

'l Electric NRC, f

~

P.rhOI'ta'aeEt'3'On

~<>>>> ~

2. I Il AP-14MO~

to Develop Cold Overpressure i!NP::-.':A'Methodology Used Li ~ i e,,"

Mitigating System Setpoints and RCS Heatup and Cooldown L-'"-.. ..=.-"'~~~96:.

p%!I""n- --iiil:"-,::: --icu!,

~ ~

d. The PTLR shall be provided to the NRC upon issuance for each reactor vessel fluencm period and for revisions or supplement thereto.

R.E. Ginna Nuclear Power Plant 5.0-22 Amendment No. Q, PP

2.0 OPERATING LIMITS The cycle-specific parameter limits for the specifications listed in Section 1.0 are presented in the following subsections. All changes to these limits must be developed using the NRC approved methodologies specified in Technical Specification 5.6.6. These limits have been determined such that all applicable limits of the safety analysis are met. All items that appear in capitalized type are defined in Technical Specification 1. 1, "Definitions."

2. 1 RCS Pressure and Tem erature Limits (LCO 3.4.3 and LCO 3.4. 12)

(Reference 1)

2. 1.1 The RCS temperature rate-of-change limits are:

a. A maximum heatup of 60'F per hour.

b. A maximum cooldown of 100'F per hour.

2. 1.2 The RCS P/T limits for heatup and cooldown are specified by Figures 1 and 2, respectively.

2. 1.3 The minimum boltup temperature, using the methodology of Reference 4, Enclosure 2 is 60'F.

2.2 Low Tem erature Over ressure Protection S stem Enable Tem erature (LCOs 3.4.6, 3.4.7, 3.4. 10 and 3.4. 12)

(Methodology of Reference 3, Attachment VI and Reference 6, as calculated in Reference 7).

2.2. 1 The enable temperature for the Low Temperature Overpressure Protection System is 322'F.

2.3 Low Tem erature Over ressure Protection S stem Set pints (LCO 3.4. 12) 2.3. 1 Pressurizer Power 0 crated Relief Valve Lift Settin Limits (Methodology of Reference 3, Attachment VI and Reference 6, as calculated in Reference 3, Attachment VII).

The liftissetting for the pressurizer Power Operated Relief Valves (PORVs) ~ 411 psig (includes instrument uncertainty).

PTLR Revision 2

Table 3 shows calculations of the surveillance material chemistry factors using surveillance capsule data.

Table 4 provides 'the reactor vessel toughness data.

Table 5 provides a summary of the fluence values used in the generation of the heatup and cooldown limit curves.

Table 6 shows example calculations of the ART values at 24 EFPY for the limiting reactor vessel material.

5.0 REFERENCES

WCAP-14684, "R.E. Ginna Heatup and Cooldown Limit Curves for Normal Operation," dated June 1996.

2. WCAP-14040-NP-A, "Hethodology Used to Develop Cold Overpressure Mitigating System Setpoints and RCS Heatup and Cooldown Limit Curves,"

Revision 2, January 1996.

3. Letter from R.C. Hecredy, RGIIE, to Guy S. Vissing, NRC,

Subject:

"Application for Amendment to Facility Operating License, Revision to Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR) Administrative Controls Requirements," dated September 29, 1997.

Letter from R.C. Hecredy, RGIIE, to Guy S. Vissing, NRC, "Clarifications to Proposed Low Temperature Overpressure Protection System Technical Specification," dated June 3, 1997.

5. WCAP-7254, "Rochester Gas and Electric, Robert E. Ginna Unit No. 1 Reactor Vessel Radiation Surveillance Program," May 1969.

6. Letter from R.C. Hecredy, RGIIE, to Guy S. Vissing, NRC, "Corrections to Proposed Low Temperature Overpressure Protection System Technical Specification," October 8, 1997.

7. RGIIE Design Analysis DA-HE-97-031, "Evaluation of Ginna RCS Coolant Temperature to Support LTOPS Requirements," Revision 0.

PTLR Revision 2

~\

~ whichever is greater. RT>>T is the highest adjusted reference temperature for weld or base metal In the beltline region at a distance one-fourth of the vessel section thickness from the vessel inside surface, as determined by Regulatory Guide 1.99, Revision 2.AIQeugh 3.4 Enable Temperature for LTOPS The enable temperature Is the temperature below which the LTOPS system is required to be operable.g ill:re,: iHWS",::: 0":- y .. ':! b~5l. I 'd':". I iiil!:iis .=.:I:. rr rl yA8taa!

CFdNCSSe~Np >4satt'te%8ME!CsdettCSSer N4g~d::SuppOrtS::a~..eoa8te.;F@8"!ITIO+dt~~epera u~r OeiiSSP~O,dred::te:,.",the'reeetsrereeeetttrat meta%tom crater;Ot"":BTtsraWSO.'.keraO'O'IIV-Ttte 3-8

whichever is greater as described In Section 3.3.ttt'Nr~dsffnitiÃfs."alsoaso cnT~d':bTrtlh14o ttfeelfnghcuaeCVmerSeCrcuy'%TfjeQInnaenableternPeratu Iedet~ennnedaa(87~+::.3'Ovs~Fj Q+!gnst~u. ~i:;:eyror Peffpw:::.:Qrnasslft~e.. peratvge~diffsreneedod:: 31'%Thssnaa~inurnha logiiwo pressure~iagii'0~of i~he atsadLatQa'e:.eve!down.;cttrve:cTNcutatsd.':.In,ac'oordancs;:wtih:fqtltendht

'8%to:,t'OCPsRSOUtj~PsrXASME~!CcdtrsCase::::M4'tsi The RCS cold leg temperature limitation for starting an RCP is the same value as the LTOPS enable temperature to ensure that the basis of the heat inJection transient is not violated. The Randar4-Technical Specifications ~prohibit starting an RCP when any RCS cold leg temperatures is less than or equal to the LTOPS enable temperature unless the secondary side water temperature of each steam generator is less than or equal to 50'F above each of the RCS COld leg temPeratureSKOrithegreeeur!Zeryat~er Valume<IS: 3%4'CnblbVafeet.':{38~741eV Jet'.

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curve (with 10% additional margin) as calculated in accordance with Appendix G to 10CFR50 or the peak RCS or RHR System pressure based upon piping/structural analysis loads. The lower pressure extreme ls specified by the reactor coolant pump P1 seal minimum differential pressure performance criteria. Uncertainties in the pressure and temperature instrumentation utilized by the LTOPS are accounted for consistent with the methodology of Reference 2.0.

Accounting for the effects of instrumentation uncertainty imposes additional restrictions on the setpolnt development, which is already based on conservative pressure limits such as a safety factor of 2 on pressure stress, use of a lower bound K,R curve and an assumed ~/iT flaw depth with a length equal to 1N times the vessel wali thickness.

3.3 Application of ASME Code Case N-514 ASME Code Case N-514II allows LTOPS to limit the maximum pressure in the reactor vessel to 110% of the pressure determined to satisfy Appendix G, paragraph G-2215, of Section XI of N

the ASME Godet'I. The application of ASME Code Case N-514 increases the operating margin in the region of the pressure-temperature limit curves where the LTOPS is enabled. Code Case N-514 also requires LTOPS to be effective at coolant temperatures less than 200'F or at coolant temperatures corresponding to a reactor vessel metal temperature, at a 1/4t distance from the inside vessel surface, less than RTgpr + 50 F, whichever is greater. RTgpy is the highest adjusted reference temperature for weld or base metal in the beltline region at a distance one-fourth of the vessel section thickness from the vessel inside surface, as determined by Regulatory Guide 1.99, Revision 2.

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I

• tt4

Enable Temperature for LTOPS The enable temperature is the temperature below which the LTOPS system is required to be operable.

The Ginna LTOPS enable temperature Is established using the guidance provided by ASME XI Code Case N-514. The ASME Code Case N-514 supports an enable RCS liquid temperature corresponding to the reactor vessel 1/4t metal temperature of RT>>r + 50'F or 200'F, whichever is greater as described In Section 3.3. This definition is also supported by the Westinghouse Owner's Group. The Ginna enable temperature is determined as (RTD~ + 50'F)

+ (instrument error I~I) + (metal temperature difference to 1/4 T). The maximum allowable pressure is 110% of the steady-state cooidown curve calculated in accordance with Appendix G to 10CFR50 'er ASME Code Case N-514i"I The RCS cold leg temperature limitation for starting an RCP is the same value as the LTOPS enable temperature to ensure that the basis of the heat injection transient is not violated. The Technical Specifications prohibit starting an RCP when any RCS cold leg temperatures is less than or equal to the LTOPS enable temperature unless the secondary side water temperature of each steam generator Is less than or equal to 50'F above each of the RCS cold leg temperatures, or the pressurizer water volume is ( 324 cubic feet (38% level).

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