ML20202F104

Forwards Responses to Questions Raised During 980109,29 & 980202 Telcons Re Power Uprate Facility OLs & TS Change Request

ML20202F104
Person / Time
Site:	Farley
Issue date:	02/12/1998
From:	Dennis Morey SOUTHERN NUCLEAR OPERATING CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20202F109	List: ML20202F104 ML20202F112
References
NUDOCS 9802190131
Download: ML20202F104 (11)

Text

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Dave Morey Southern Nucleat We Presdent Operating Compar.y Iatley Project PO Bn1795 Birmingham. .%t ama 35201 Tel 205.932 5131 Fcbruary 12, 1998 SOUTHERN COMPANY Energy to Serre 11rur%rld*

Docket Nos. 50 348 10 CFR 50.90 50-364 U. S. Nuclear Regulatory Commission ATFN.: Document Control Desk Washington,DC 20555 l Joseph hl. Farley Nuclear Plant Response to Request fur Additional leformation Related to Power Uprate

[acility Operatiegligenses and Technical S.nqqifications Channe Reaunt Ladies and Gentlemen:

By letter dated February 14,1997, St,uthern Nuclear Operating Company (SNC) proposed to l amend the Facihty Operating Licenses and Technical Specifications for Joseph ht. Farley Nuc' ear Plant (FNP) Unit I and Unit 2 to allow operation at an increased reactor core power level of 2775 megawatts thermal (htwt). NRC letters dated July 1,1907; August 21,1997 and October 14, 1997 res;uested SNC provide additional information. SNC responded by letters dated August 5, 1997; September 22,1997; and November 19,1997 respectively. SNC letters dated December 17 and 31,1997 and January 23,1998 responded to NRC questions resulting from conference calls.

During telephone conference calls on January 9 and 29,1098 and February 2,1998, SNC responded to additional NRC Staff questions. Attachment i provides the SNC responscs to these questions. Attachment 11 includes revisions to the Upper Shelf Energy Summary Report.

(Reference Attachment 11 of SNC letter dated August 5,1997.) Attachment til includes a icvision to the proposed changes to Technical Specifications page 6-19a for power uprate. (Reference Attachment 111 of SNC letter dated February 14, 1997.) The basis for revising page 619a follows.

In letter dated November 19,1997, SNC responded to NRC Question No. 3 pertaining to the Technical Specifications and FSAR references associated with the use of VANTAGE + fuel (i.e.,

VANTAGE 5 with ZlRLOS clad fuel) at Farley. After further consHeration, SNC and Westinghouse have determined that WCAP 12610 P A,"VANTAGd+ Fuel Assembly Reference Core Report," should be included as a Core Operating Limits Report (COLR) reference document in the FNP Technical Specifications Administrative Controls Section. Specifical',, the proposed power uprate onanges to Section 6.9.l.11.3 will be revised to include WCAP.12610-P A as reference item No. 3d. This reference is a minor administrative change and should be added

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because it reflects the latest NRC-approved methodology used for the rod heatup calculation in the Best Estimate LOCA evaluation model with consideration for ZlRLON clad fuel properties, which supports the llcat Flux Ilot Channel Factor analysis. As such, the addition of WCAP 12610-P A satisfies the Technical Specification 6.9.1.11 requirement to list the NRC approved analytical i methods used to determine the core operating limits. This change does not affect the February 14, g 199710 CFR 50.92 signifwant hazards evaluation conclusions that the proposed changes do not l

involve a signification hazard consideration.

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Respectfully submitted, SOUTl!ERN NUCl. EAR OPERATING COMPANY f V )?pfwf .

Dave Morey Sworn to andsubscribed be >re me thishaay ofh.LJ998

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P ATTACitMENT I l

4 SNC Response to NRC Request For Additionalinformation l Related To Power Uprate Submittal . Joseph M. Farley Nuclear Plant, Units 1 and l SNC RESPONSES TO NRC QUESTIONS RESULTING FROM NRC/SNC CONFERENCE CALLS ON JANUARY 9 AND 29,1998 A

9 SNC Response to NRC Request For AdditionalInformation Related To Power Uprate Submittal Joseph M. Farley Nuclear Phnt. Units 1 and 2 NRC Ouestion No 1 (LeferenceJanuary 9.1998_and February 2.1998 NRC/SNC Conference Calls and February 2.199J NRC Facsimile) llave the change: being made to the plant, associated with the power uprate, increased the probability or created the possibility of a steam generator tube rupture with stearn generator overfill. If so. shat is bdng done to preclude steam generator overfdl as a correquence of a tube rupture?

SNC ResnonseRd i

he Farley licensing basis steam generator tube rupture (SGTR) analysis consists of a simple mass and energy balance to calculate the primary to secondary break flow and atmosphenc steam releases from the ruptured and intact steam generators for use in calculating the ofTsite radiological doses. This calculation wat re performed specifically at the uprated power conditions. The results are presented in Section 6.3 of the NSSS 1,icensing Report OVCAP 1472.4).

A detailed analysis of the steam generator tube rupture event was not required prior to the SOTR which occurred at the Ginna Plant in January,1982. Following that event, the traditional assumptians used in FSAR analysis of a design basis SGTR wem questioned. In addition, consideration of the possibility of overfill of the ruptured steam generator and potential single failures not traditionally included in the SGTR analyses was also investigated. De methodology provided by References I and 2 was developed to respond to these concems by the SOTR Subgroup of the Westinghouse Owners Group OV00) and was approved by the NRC in Safety Evaluation Reports dated December 17,1985 and March 30,1987. Th;NRC has not required plants licensed prior to the Ginna event to perform analyses to verify margin to steam generator overfill.

Dae to the vintage of the plant license, margin to steam generator overfill analyses have not been performed for Farley and are not part of the current Farley licensing basis. Nevertheless, the NRC has requested confirmation that the changes made to the plant associated with the power uprating do not increase the probability or create the possibility of r steam generator tube mpture with steam generator overfill. Since the Farl~ Nensing buis does not include a margin to overfill analysis, this question is best addressed by examining analyses performed for plants licensed with the methodology deve!oped in References I and 2. In response to an NRC verbal request (February 2,1998), a four loop Westinghouse plant which has uprated and with a margin to steam generator overfill calculation in the licensing basis documentation has been identified. He uprating analysis for this plant modeled an uprating and associated changes including steam generator level tap relocation. The analysis concluded that the cumulative effects of these changes has a m'mr impact on the margin to overfill for a steam generator tube rapture and even resulted in a small inumase in margin.

Since analyses for other plants with similar design configuration have demonstrated that an uprating and associated changes do not increase the probability of a steam generator tube rupture with steam generator overfill, the Farley uprating should not increase the possibility or prcbability of a steam generator tube rupture with steam generator overfill.

PageI

Ikspgnse No. I References '

l. WCAP.10698 P A,"SGTR Analysis Methodology to Determine the Margin to Steam Generator Overfill," August 1987.

2. Supplement I to WCAP.10698 P A," Evaluation of Offsite Radiation Doses for a Stearn Generator Tube Rupture Accident," March 1986.

W/ub d.jm . 2/6/98 NRC Ouestion No. 2 NRC Question No. 2 (Reference January 29.1998 NRC/SNC Conferenst C all & NRC Facsimik)

Attachment 11 to the August 5,1997 SNC RAI response provided marked up changes to the Farley Unit I and Unit 2 Upper Shelf Energy Summary Report and PTS Summary Report associated with the NRC - Reactor Vessel Integrity Database. These changes were based on revised fluence and chemical composition from the July 23,1997 SNC Technical Specifications Change Request -

Pressure Temperature Limits Report. Subsequent revisions to the PTLR submittal (SNC letter dated December 18,1997) have affected the marked up changes provided on August 5,1997.

Please provide new marked-up changes to the Farley Unit I and Unit 2 Upper Shelf Energy Summary Report.

SNC Response No. 2 Attachment 11 provides the requested information based on the most current data for Farley Unit 1 ed Unit 2.

SNC/tws . 2/1C/98

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ATTACllMENT 111 4 4 SNC Response to NRC Request For Additionalinformation Related To Power Uprate Submittal . Joseph M. Farley Nuclear Plant Units 1 and 2 FNP Unit i Technical Specifications Changed Page List FNP Unit i Technical Specifications Marked-up Page FNP Unit i Technical Specifications Typed Page FNP Unit 2 Technical Specifications Changed Page List FNP Unit 2 Technical Specifications Marked up Page FNP Unit 2 Technical Specifications Typed Page l

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FNP Unit i Technical Specifications Power Uprate implementation ChWIsLPac Umt i Gension Page 6-19a New Page (Replace TS Page 6-19a in February 14,1997 Submittal) i