ML20073D432
| ML20073D432 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 09/22/1994 |
| From: | Link B WISCONSIN ELECTRIC POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML19304C537 | List: |
| References | |
| CON-NRC-94-069, CON-NRC-94-69 VPNPD-94-101, NUDOCS 9409270200 | |
| Download: ML20073D432 (2) | |
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Wisconsin Electnc POWER COMPANY 231 W Mchgan. PO Box 2046. Mdwoukee.WI S32012046 (414)221-2345 VPNPD-94-101 10CFR50.4 NRC-94-069 10CFR50.90 September 22, 1994 Document Control Desk U.S. NUCLEAR REGULATORY COMMISSION Mail Station P1-137 l
Washington, DC 20555 I
Gentlemen
- l DOCKETS 50-266 AND 50-301 RESPONSE TO REOUESTS FOR ADDITIONAL INFORMATION TECHNICAL SPECIFICATIONS CHANGE REOUEST 175 POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 On August 26, 1994, we submitted Technical Specifications. Change Request 175, " Modifications to Section 15.4.2,
'In-Service Inspection Of Safety Class Components,'" which-requested amendments to Facility Operating Licenses DPR-24 and DPR-27 for Point Beach Nuclear Plant, Units 1 and 2, respectively.
The proposed changes modified Technical Specifications Section 15.4.2, "In-Service Inspection of Safety Class Components," by incorporating the use of acceptance criteria to allow sleeved tubes with certain upper sleeve joint parent tube indications to remain in s,rvice as described in Westinghouse WCAP-14157, " Technical Evaluation of Hybrid Expansion Joint (HEC) Sleeved' Tubes Containing Indications Within the Upper Joint Zone."
On September 1, 7, and 9, 1994, you transmitted questions requesting additional information regarding our August 26, 1994, submittal.
We provided responses to these questions in a letter dated September 13, 1994.
On September 16 and 19, 1994, you transmitted additional questions regarding our submittal.
Enclosed are responses to these questions.
In order to facilitate our responses, the questions have been categorized as follows:
Structural Integrity Projected Leak Rates Corrosion Cracking-Non-Destructive Examination Structural and Leak Rate Testing HEJ Operating Experience Plant Operation Risk Assessment 9409270200 940922
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Document Control Desk l
September 22, 1994 Page 2 The numbering preceding each question corresponds to the date that the question was transmitted to Wisconsin Electric Power Company and the question number from the associated transmittal.
These responses contain-information which is proprietary to Westinghouse Electric Corporation.
Accordingly, we request that this information be withheld from public disclosure.
We will comply with the requirements of 10 CFR 2.790 to provide a non-
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proprietary version of this material together with an affidavit as soon as the non-proprietary version has been prepared.
We will submit the required number of copies of the non-proprietary i
version of the'information and the required affidavit at that time.
In the meantime, we are providing the proprietary version for your information and use.
Please contact us if you have any questions.
Sincerely, I
/d Bob Link Vice President Nuclear Power DAW /jg Enclosures cc:
NRC Regional Administrator NRC Resident Inspector l
Public Service Commission of Wisconsin l
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