RC-99-0201, Suppl 2 to 990819 Application for Amend to License NPF-12 (TSP 980009),revising Heatup & Cooldown Curves in TS 3/4.4.9 RCS Pressure/Temp Limits & TS B 3/4.4.9.Rev 2 to WCAP-15102 Encl

Suppl 2 to 990819 Application for Amend to License NPF-12 (TSP 980009),revising Heatup & Cooldown Curves in TS 3/4.4.9 RCS Pressure/Temp Limits & TS B 3/4.4.9.Rev 2 to WCAP-15102 Encl

ML20217D625
Person / Time
Site:	Summer
Issue date:	10/08/1999
From:	Gabe Taylor SOUTH CAROLINA ELECTRIC & GAS CO.
To:	Cotton K NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20217D630	List: ML20217D635 ML20217D640 RC-99-0201, Suppl 2 to 990819 Application for Amend to License NPF-12 (TSP 980009),revising Heatup & Cooldown Curves in TS 3/4.4.9 RCS Pressure/Temp Limits & TS B 3/4.4.9.Rev 2 to WCAP-15102 Encl
References
RC-99-0201, NUDOCS 9910180027
Download: ML20217D625 (6)

Text

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L SCE&G. A SCANA COMPANY

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Document Control Desk J U. S. Nuclear Regulatory Commission 5 Washington, DC 20555 m;j

' Attention: Ms. K. R. Cotton

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4 Gentlemen:

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. ( Gwy J. TEylw

Subject:

VIRGIL C. SUMMER NUCLEAR STATION vicehesident u DOCKET NO. 50/395 Nudec 0peeriss OPERATING LICENSE NO. NPF-12 TECHNICAL SPECIFICATION CHANGE REQUEST -TSP 980009

- SUPPLEMEF 2 REACTOR COOLANT SYSTEM - HEATUP/COOLDOWN CURVES

^

Reference:

Gary J. Taylor, SCE&G, to NRC, RC-98-0185, October 9,1998 A Gary J. Taylor, SCE&G, to NRC, RC-99-0030, February 18,1999 x Gary J. Taylor, SCE&G, to NRC, RC-99-0152, August 19,1999 Gary J. Taylor, SCE&G, to NRC, RC-99-0154, August 19,1999 South (soline

Dearic & Gas Co Note:

This letter supplements the above referenced letter dated August 19, i Virgil C Summer Mar Station >

1999 (RC-99-0154).

< P. 0 Box . .

ville. South Carolina .

South Carolina Electric & Gas Company (SCE&G), acting for itself and as agent for South Carolina Public Service Authority, hereby requests an amendment to the Virgil 803.345.4344 : C. Summer Nuclear Station (VCSNS) Technical Specifications (TS). This request is i 03.345.5m 8

being submitted pursuant to 10 CFR 50.90. This Technical Specification Change wwwsencar Request supplements the change request datec August 19,1999 in that the flange temperature requirement portion of the previous request is being withdrawn and has p*

been removed from this change request.

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o

, The proposed changes will revise the heatup and cooldown curves located in TS section 3/4.4.9 Reactor Coolant System Pressurefremperature Limits and the Technical Basis of TS Section B 3/4.4.9. This change is required since the current

, curves are only applicable to 13 Effective Full Power Years (EFPY) and will expire on 0

. or after October 23,1999. 0 t

SCE&G desires that this change be approved by October 18,1999, to permit implementation of the change, including training, prior to exceeding the applicability of the current Heatup/Cooldowngurves.

x .w -. j.Y l- 9910100027 991008-

{ PDR ADOCK 05000393 P PDR NUCLEAR EXCELLENCE - A SUMMER TRADITION!

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Docum:nt Control D:sk

." TSP 980009 RC-99-0201 Page 2 of 3 Enclosed is WCAP-15102, Revision 2, V. C. Summer Unit 1 Heatuo and Cooldown Limit Curves for Normal Operation. This report details the development of the revised heatup and cooldown curves based on the data obtained from the analysis of surveillance capsule W, removed from the V. C. Summer's reactor vessel in October 1997. The analysis on this specimen was sent to the USNRC via SCE&G letter dated October 9,1998.

The curves presented in this WCAP were developed using guidance located in 10 CFR 50,

- Appendix G, and meet the criteria of Appendix G to the ASME Boiler and Pressure Vessel Code,Section XI. ' The curves provided by this proposed change do not include instrument uncertainties. The curves that will provide operational limitations will be located in plant operating procedures, instrument uncertainties, elevation differences between the RCS pressure sensing instruments and the reactor vessel beltline, and the effect of forced flow are factored into developing the operational limitations.

Included in the methodology for the generation of these curves is the utilization of the 1996 ASME Boiler and Pressure Vessel Code,Section XI, Appendix G, along with ASME Code Case N-640. Reference 3 is the Exemption Request to permit utilization of the alternative methodology.

The Low Temperature Over-Pressurization (LTOP) protection setpoint was also reviewed using the data provided in the WCAP. For the most limiting transient condition, the setpoint remains adequate to satisfy the ASME Code,Section XI, Appendix G requirements.

The TS change request is contained in the following attachments:

Attachment i Explanation of Changes Summary Merked-up Technical Specification Pages Revised Technical Specification Pages Attachment 11 Safety Evaluation Attachment lil No Significant Hazards Evaluation This proposed amendment has been reviewed and approved by the Plant Safety Review Cornmittee and the Nuclear Safety Review Committee.

These statements and matters ses forth herein are true and correct to the best of my knowledge, information, and belief.

Should you have questions, please call Mr. Philip A. Rose at (803) 345-4052.

Very trul yours, 6 Q S& M.T Gary J. Taylor PAR /GJT/dr Attachment c: See page 3

n Docum:nt Control Desk TSP 980009 RC 99-0201 Page 3 of 3 c: J. L. Skolds W. F. Conway R. R. Mahan (w/o Attachment)

R. J. White L. A. Reyes NRC Resident inspector  !

Paulett Ledbetter J. B. Knotts, Jr.  !

M. K. Batavia C. C. Barbier i NSRC RTS (TSP 980009)

File ,(813.20)

DMS (RC-99-0201) i i

i i

STATE OF SOUTH CAROLINA  :

TO WIT : I l COUNTY OF FAIRFIELD  :

I hereby certify that on the 8 day of Ockclav 19 9 9. before me, the subscriber, a Notary ,

Public of the State of South Carolina personally appeared Stephen A. Byrne, being duty sworn,  ;

L and states that he has signature authority for the Vice President, Nuclear Operations of the South l l Carolina Electric & Gas Company, a corporation of the State of South Carolina, that he provides

! the foregoing response for the purposes therein set forth, that the statements made are true and correct to the best of his knowledge, information, and belief, and that he was authorized to l provide the response on behalf of said Corporation. '

I WITNESS my Hand and Notarial Seal Notarf4)ublic My Commission Expires MyComds&n Er[es My'13. 2005',

Date t ; :.:

c i 1

1

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Document Control De:k Attachment I

, TSP 980009 RC-99-0154 Page 1 of 3 SCE&G - EXPLANATION OF CHANGES Affected Page Section Bar # Description Reason Index XIll B 3/4.4.5 1 Renumbered such that index Mistake made to index during i through match Bases. originalissuance of Tech B 3/4.4.10 Specs.

3/4 4-31 Figure 3.4-2 1 Revised Figure 3.4-2 heatup Curves revised due to rates curves for 32 EFPi. analysis of surveillance specimen capsule W.

3.4-2 for applicability to 32 analysis of surveillance EFPY. specimen capsule W.

3/4 4-32 Figure 3.4-3 1 Revised Figure 3.4-3 Curves revised due to cooldown rates curves for 32 analysis of surveillance EFPY. specimen capsule W.

3.4-3 for applicability to 32 analysis of surveillance EFPY. specimen capsule W.

B 3/4 4-6 B 3/4.4.9 1 Revised ASME B&PV code Section XIincorporated reference from Section lil to Appendix G; 1996 ASME Section XI, changed to 1996 Code and Code Case used to Section XI, Appendix G, develop new P-T curves.

Included reference to WCAP-14040, included reference to ASME Code Case N-640 B 3/4 4-7 B 3/4.4.9 1 Changing methodology of Curves were calculated using calculating P-T Limit lines updated methodology which required prior NRC approval.

2 Deleted bottom half of page. Updated methodology can now be found in WCAP 14040 and WCAP 15102, Revision 2.

B 3/4 4-8 8 3/4.4.9 N/A Deleted page Updated methodology can now be found in WCAP 14040 and WCAP 15102, Revision 2.

B 3/4 4-9 Table N/A Deleted page Updated methodology can B 3/4.4-1 now be found in WCAP 14040 and WCAP 15102, Revision 2, Table now found in WCAP 15102, Revision 2

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- Attachment 1 TSP 980009 RC-99-0154 Page 2 of 3 SCE&G - EXPLANATION OF CHANGES Affected Page Section Bar # Description Reason B 3/4 4-10 B 3/4.4.9 N/A Figure B 3/4 4.1 deleted. Figure located in Regulatory Guide 1.99, Revision 2.

B 3/4 4-10a B 3/4.4.9 N/A Figure B 3/4 4.2 deleted and Figure located in Regulatory Page removed. Guide 1.99, Revision 2.

B 3/4 4-11 B 3/4.4.9 N/A Deleted page Updated methodology can now be found in WCAP 14040 and WCAP 15102, Revision 2.

B 3/4 4-12 B 3/4.4.9 N/A Deleted page Updated methodology can now be found in WCAP 14040 and WCAP 15102, Revision 2.

B 3/4 4-13 8 3/4.4.9 N/A Deleted page Updated methodology can now be found in WCAP 14040 and WCAP 15102, Revision 2.

B 3/4 4-14 8 3/4.4.9 1 Added subtitle Keep consistency of Bases

" PRESSURE /I'EMPERATURE titles.

LIMITS (Continued)".

now be found in WCAP 14040 and WCAP 15102,

=..... ........ . ... ...- - -... .

Revision 2.

WCAP 15102, Revision 2. generated and presented

2. Deleted last sentence of in this WCAP.

paragraph. 2. Curves based on Methodology in WCAP-14040-NP-A, not

. . . . . . . . . . . . = - - . . ..... .... . ... -- ......

Standard Review Plan.

designation. Removed recently removed and discussion of weld metal. analyzed. Clarified the most Revised limiting material heat limiting reactor vessel numbers. Provided new ART materials. Provided new limits / neutron fluence limits from analysis of location. Provided calculated Capsule W. Provided value at new curve bounding values for applicabilitylimit. Deleted applicability of pressure /

unnecessary information. temperature limits curves.

Removed information that is no longer required or is incorrect.

t Docum:nt Control Dnk Att chm:nt i TSP 980009

. RC-99-0154 Page 3 of 3 SCE&G - EXPLANATION OF CHANGES Affected Page Section Bar # Description Reason B 3/4 4-14 B 3/4.4.9 5 Added clarification to Provided lead-in to discussion Continued sentence. of criticality on pressure /

temperature limits.

opposed to using footnotes. into body of text.

impact on the requirements of impacts on stress intensity ASME Code and 10 CFR 50, factor and margin provided.

Appendix G.

8 Added discussion on handling TS curves no longer contain of instrument uncertainties. uncertainties; heatup/

cooldown curves in operating procedures contain adjustments for uncertainths and other effects.

into body of text.

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