ML20198D984
| ML20198D984 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 11/24/1992 |
| From: | Link B WISCONSIN ELECTRIC POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML19310D503 | List: |
| References | |
| CON-NRC-92-139 IEB-88-011, IEB-88-11, TAC-M72155, TAC-M72156, VPNPD-92-360, NUDOCS 9212030274 | |
| Download: ML20198D984 (4) | |
Text
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a3 Wisconsin
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\\ Elecinc POWER COMPANY 234 W McNgart PO Box 204$ M1wovkee va 53201 (414)221 1345 R
E VPNPD 360 NRC-92-139 November 24, 1992 d
i g
R Document Control Desk U.S. NUCLEAR REGULATO.,Y COMMISSION Mail Station P1-137 4
Washington, DC 20555
$a Gentlemen:
DOCKET 50-266 AND 50-301 7
COMPLETION OF THE REPORTING REOUIREMENTS FOR ACTION ITEM 1.d f
OF NRC IE BULLETIN 88-11 (TACsaO2155 AND472156) j POINT BEACH NUCLEAR PLANT. UNITS 1 AND 2 4
1 3~
In a letter dated March 25, 1992, (see Attachment 1, Reference 7),
Wisconsin Electric Power Company notified the Nuclear Regulatory Commission (NRC) that we were initiating new plant specific arialyses to satisfy the reporting requirements of NRC Bulletin 88-11, " Pressurizer Surge Line Thermal Stratification."
These analyses were required to quantify the effects of the
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occurrences for which Point Beach Nuclear Plant (PBNP) Units 1 and 2 had operated above the Westinghouse owners Group system delta T analysis limit of 210*F (the difference between the pressurizer and hot leg temperatures).
Our March 25, 1992, letter y
concluded by stating that the analyses would be finished by the end
.of November-1992.
This letter transmits the Westinghouse Electric Corporation analysis results and completes all cf the Bulletin 2
reporting requirements for PBNP Units 1 and 2.
2 The PBNP pressurizer surge lines are supported by three spring supports on each unit.
No rigid restraints exist on either lisie.
E The analyssr, results demonstrate that all spring hangers are within their res w cive load capacities ani travel distances with the exceptior.;n the travel allowance for-Unit i Spring Hanger RC-2.
The Unit i analysis assumes that-the existing RC-2 support will be modified during the spring 1993 refueling outage to provide a 1
greater travel allowance, and consequently envelopes both the existing and future support configurations of the surge line, i
Therefore, the pressurizer surge lines meet the ME Boiler and 3
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Document Control Desk' February 24, 1992 Page 2 Pressure vessel Code,Section III, " Rules for Construction of Nuclear Power Plant Components," 1986 edition, pipe stress and fatigue limit allowables for the remainder of the licensed operation 1of both units.
The analysis results also conclude there is no contact between the pressurizer surge line and the pipe whip restraints on either unit.
Therefore, no whip restraint modifications are necessary for Code compliance.
In summary, the analyses demonstrate Code compliance for Units 1 and 2 as specified in the reporting requirements of NRC Bulletin 88-11.
The analysis results are documented in WCAP-13509 and WCAP-13510,
" Structural Evaluation of the Point Beach Units 1 and 2 Pressurizer Surge Lines, Considering the Effects of Thermal Stratification,"
dated October 1992.-
WCAP-13509 is the Westinghouse-Proprietary Class 2 version of the analysis and WCAP-13510 is the Westinghouse Proprietary Class 3 version.
Copies of both WCAP-13509 and WCAP-13510 are enclosed with this letter.
Also enclosed with this letter is the Westinghouse Authorization Letter, " Application for Withholding Proprietary Information from Public Disclosure," Letter CAW-92-370, identifying WCAP-13509 as containing proprietary information and requesting that this information be withhe13 from Public disclosure.
To support the request for withholding the information contained in WCAP-13509 from public disclosure, copies of a signed " Affidavit," the
" Proprietary Information Notice," and the required non-proprietary version of the analysis results (WCAP-13510) are enclosed, along with a Westinghouse Electric Corporation " Copyright Notice" applicable to the submitted documents.
Accordingly, it is requested that the information which has been identified as proprietary to Westinghouse be withheld from public disclosure in accordance with 10 CFR Section 2.790 of the Commissior.~s regulations.
In conjunction with the above referenced analyses, we have revised the ELNP operating procedures for heatup and cooldown to ensure that future operation of the-ple.nt will be within the system delta T limit of 210*F as assumed in the analyses.
The results of these combined efforts have led to the conclusion that, once the travel allowance for Unit 1 Spring Hanger RC-2 has been modified, Point Beach Nuclear Plant Units 1 and 2 will be in full compliance-with the requirements of NRC Bulletin 88-11.
Document Control Desk November 24, 1992 Page 3 We would be pleased to discuss this with you at your_ convenience if you so desire.
Please contact us if you have any questions regarding this matter.
Sincerely,
(
l l
Bob Link Vice President Nuclear Power MAW /jg Attachment cc:
NRC Regional Administrator-Region III NRC Resident Inspector i
Subscribed and sworn-to before me
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this ) V" day of 7 6 kn_, 1991.
0DJ. b,1 frUb LS 1:
ty0Public, state of Wisconsin My commission expires so-a;-%.
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ATTAC} DENT _1
References:
1)
Wisconsin Electric Power Company Letter VPNPD-89-314, dated 05/31/89, to the NRC on the subject of " Submittal of Justification for Continued Operation Regarding Pressurizer Thermal Stratification, Point Beach Nuclear Plant Units, 1 and 2."
2)
Letter from the NRC to C.
W.
Fay, dated 09/25/90, on the subject of "NRC Bulletin No. 88-11, Pressurizer Surge Line Thermal Stratification - Evaluation of WOG Bounding Analysis (Tack 72155 and 72156)."
3)
Wisconsin Electric Power Company Letter VPNPD-90-498, dated 12/18/90, to the NRC on the subject of " Request for Extension of Analysis Completion Date per Item 1.d of NRC IE Bulletin 88-11."
4)
Wisconsin Electric Power Coppany Letter VPNPD-91-184, dated 06/07/91, to the NRC on the subject of " Plant Specific Thermal 4
Stratification Analysis Results and Completion Date Extension Request for Completion of Action Item 1.d of NRC IE Bulletin 88-11."
5)
United Stater Nuclear Regulatory Commission Letter (Docket Nos. 50-266, and 50-301), dated 08/16/91, to Wisconsin Electric Power Company on the subject of " Pressurizer Surge Line Thermal Stratification, Bulletin 88-11 (Tack Nos. 72155 and 72156).
6)
Wisconsin Electric Power _ Company Letter VPNPD-91-452, dated 12/19/91, to the NRC on the subject of " Program Status Update and Extension Request for Completion of Action Item 1.d of NRC IE Bulletin 88-11."
7)
Wisconsin Electric Power Company Letter VPNPD-92-138, dated 03/25/92, to the NRC the Subject of " Program Status Update for Completion of Action Item 1.d of NRC IE Bulletin 88-11."