ML20083D269
| ML20083D269 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 09/23/1991 |
| From: | William Cahill TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| TXX-91350, NUDOCS 9109300126 | |
| Download: ML20083D269 (4) | |
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Log # TXX-91350
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File # 10010 22' TZ 916 (6.0) 1UELECTRIC September i'3.1991 Williara J. Cahill, Jr.
Lxecutm Vw 1%sukm U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington. D. C.
20555
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES). UNIT 1 DOCKET NO. 50-445 OPERATING LICENSE NPF 87 TECHNICAL SPECIFICATION SUBMITTAL ON CORE OPERATING LIMITS REPORT REF:
TU Electric letter logged TXX-91179 from William J. Cahill, Jr., to the NRC. dated May 24, 1991.
Gentlemen:
Via the referenced totter and pursuant to 10CFR50.90. TU Electric requested a".
amendment to its Operating License NPt-87 by incorporating propojed changes to the Technical Specification for CPSES Unit 1.
When implemented, this License Amendment Request (LAR)-91-007 would allow, among other things, the relocation of cycle specific pcrameters to a Core Operating Limits Report. The specifics concerning this report are contained in the requested changes for Administrative Control section 6.9.1.6.
During the review of LAR-91-007, the NRC staff questioned the report date identified for WCAP-8200, and the duplicate alpha characters in section 6.9.1.6.
The date identified in LAR-91-007 as the issue date for WCAP-8200.
Revision 2. is July, 1974.
That dite is the date of issue for the non-proprietary version of the report and of submittal for both versions to the NRC staff.
It is more appropriate to reference the actual date on WCAP-8200 Revision 2, which is June, 1974.
The alpha characters in section 6.9.1.6 for the list of refer 6 aces (WCAPs) are unnecessary since specific WCAPs can be identified by their report numbers.
Attached are the at ked-up subject pages ra*lecting the discussion above.
In addition, the NRC pointed out that the TU Electric generated Core Operating Limits Report (preliminary version to support the License Amendment Request review) contained a figure for control rod insertion limits which (like the current Technical Specifications) did not reference the position of control bank A.
In order to ensure that an insertion limit is specified for all control banks. TV Electric will include the limit for control bank A in the approved version of the Core Operating Limits Report.
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,4 400 North Olive Strett L.B. 81 Dallas, Texas 75201 i
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TXX-91350 Page 2 of 2 If you should have additional questions please contact Mr. Jimmy Seawright at 214/812-4375.
Sincerely.
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WilliamJ.C(hillJr.
JDS/gj cc: Mr. R. D. Martin. Region IV Resident inspectors. CPSES (2)
Mr. T. A. Bergman, NRR l
I
Attachment to TXX-91350 Page 1 of 2 ecRE OPERATING LIMITS REPOHI 6.9.1.6 Core operating limits shall be established and documented in the CORE OPEP.ATING LIMITS REPORT (COLR) before each reload cycle or any remaining part of a reload cycle for the following:
a.
Moderator temperature coef ficient BOL and EOL limits and 300 ppm surveillance limit for Specification 3/4.1.1. 3, b.
Shutdown Rod Insertion Limit for Specification 3/4.1. 3. 5, c.
Control Rod Insertion Limits for Specification 3/4.1. 3.6, d.
AXIAL FLUX DIFFERENCE Limits and target band for Specification 3/4.2.1, e.
Heat Flux Hot Channel Factor, K(Z), W(Z), and Ff for Specification 3/4.2.2,
[
f.
Nuclear-Enthalpy Rise Hot Channel Factor Limit and the Power Factor Multiplier for Specification 3/4.2.3.
The analytical methods used to determine the core operating limits shall be those previously approved by the NRC in:
Y ' WCAP-9272-P-A,
" WESTINGHOUSE RELOAD SAFETY EVALUATION METHODOLOGY", July 1985 (H Proprietary).
-(Methodology for Specifications 3.1.1.3 Moderater Temperature Coefficient, 3.1.3.5 Shutdown Bank Insertion Limit, 3.1.3.6 - Control Bank Insertion Limits, Axial Flux Dif ference, 3.2.2.
3.2.1 Heat Flux Hot Channel Factor, and 3.2.3 Nuclear Enthalpy Rise Hot Channel Factor.)
WCAP-8385, " POWER DISTRIBUTION CONTROL AND LOAD FOLLOWING PROCEDURES TOPICAL REPORT",
September 1974 (H
Proprietary).
(Methodology for Specification 3.2.1 Axial Flux Difference (Constant Axial Offset Control).)
o T.
M.
Anderson to K. Kniel (Chief of Core Performance Branch, NRC January 31, 1980--Attachment : Operation and Safety Analysis Aspects of an Improved Load Follow Package.
(Methodology) for Specification 3.2.1 Axial Flux Difference (Constant Axial Offset Control).)
NUREG-0800, Standard Review
- Plan, U.
S.
Nuclear Regulatory Commission, Section 4.3, Nuclear Design, July 1981.
Dranch Technical Position CPB 4.3-1, Westinghouse Constant Axial Offset Control (CAOC), Rev. 2, July 1981.
(Methodology for Specification 3.2.1 Axial Flux Difference (Constant Axial Offset Control).)
1
l
, ' Attachment to TXX-91350 Page 2 of 2 v
" RELAXATION OF CONSTANT AXIAL OFFSET CONTROL FQ SURVEILLANCE TECHNICAL SPECIFICATION", June 1983 (H Proprietary).
(Methodology for Specification 3.2.2-Heat Flux Hot Channel Factor (W (t) surveillance requirements for F.
Methodology).)
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WCAP-8200, "WFLASH, A FORTRAN-IV COMPUTER PROGRAM FOR SIMULATION OF TRANSIENTS IN A MULTI-LOOP PWR,"
Revision (f
T, M 1974 (W_ Proprietary).
(Methodology for Specification 3.2.2 Heat Flux Het Channel Factor))r.)
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" Westinghouse ECCS Evaluation
- McCal, February 1978 Version," February 1978 (H Proprietary).
(Methodology for Specification 3.2.2 Heat Flux Hot Channel Factor The core operating limits shall be determined so that all j
applicable limits (e.g.,
fuel thermal-mechanical
- limits, core thermal-hydraulic limits, ECCS limits, nuclear limits sv s as shutdown margin and transient and accident analysis limits) or the safety analysis are met, j
The CORE OPERATING LIMITS REPORT, including any mid-cycle revisions or supplements thereto, shall be provided upon issuance, for e!ch reload cycle, to the NRC Document Control Desk with copies to the Regional Administrator and Resident Inspector.
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