ML20032D523
| ML20032D523 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 11/09/1981 |
| From: | Carey J DUQUESNE LIGHT CO. |
| To: | Varga S Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20032D524 | List: |
| References | |
| TAC-47357, TAC-47358, TAC-47359, NUDOCS 8111170215 | |
| Download: ML20032D523 (3) | |
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M (4m 4564000 lf,f;",,'y November 9, 1981 15219 I
Dire'ctor of Nuclear Reactor Regulation e
United States Nuclear Regulatory Commission Attn:
Mr. Steven A. Varga, Chief g3 Operating Reactors Branch No. 1 of
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Division of Licensing Washington, DC 20555
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Reference:
Beaver Valley' Power Station, Unit No. 1 O
Docket No. 50-334, License No. DPR-66
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Proposed Change Request No. 65 to Operating Licens g
Gentlemen:
Enclosed are three (3) originals and thirty-seven (37) copies of proposed change Request No. 65 to the Beaver Valley Power Station, Unit No. l' Technical' Specifications Appendix A.
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Attachment A, Table 3.3-3 changes the Solid State Protection System channel surveillance allowable testing period from one (1) to two (2) hours. Attachment B. Section 4.6.1.2 updates the method used for containment leak rate testing from the provisions of ANSI N45.4-1972 to ANSI N56.8-1981. Attachment C, Table 3.6-1
" Containment Isolation Valves" Section C has been changed such that the contain-ment purge and exhaust valve isolation times are applicable in Mode 6 only.
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Section 3.9.4 and 3.9.9 have been changed to reference Table 3.6-1.
Attachment D, i
Section 4.4.5.2 has been revised to reference the ASME Boiler and Pressure Vessel Code Section XI Appendix IV as amended in the Summer 1976 addenda for Steam Generator tube sample selection and inspection. Attachment E, Section 4.4.10b has been revised to permit the use of an alternate examination schedule for the Reactor Vessel nozzle to safe end welds.
Safety Evaluation l
Attachment A, the purpose for changing the allowable testing period of the Solid-State Protection System channel surveillance requirement from one l
(1) to two (2) hours on Table 3.3-3 is to allot sufficient time for the j
testing to be performed in a realistic time frame due to increased testing l
requirements imposed since 1976. Attachment B, Sectic 4.6.1.2 has been updated to provide for testing some containment penetrations using water as the pressurized fluid during Type C leak testing as recognized by the provisions of ANSI N56.8-1981.
Attachment C, Table 3.6-1 has been changed because the stroke times for the Containment Purge and Exhaust Valves are only required for fuel handling accidents i
and will provida for fully opening the valves in Mode 5 for better purge capability with stroke times on the order of 12 seconds.
Section 3.9.4 and 3.9.9 have been changed to reflect the reference to Table 3.6-1 when testing the Isolation Times of the containment purgo and exhaust valves.
Attcchment D, Section 4.4.5.2 has
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r Beaver Valley Power Station, Unit No. 1 Docke t No. 50-334, License No. DPR-56 Proposed Change Request No. 65 to Operating License Page 2 changed because the Technical Specifications presently recognize the ASME Section XI 1974 edition through the 1975 Summer Addenda, a review of the ASME Section XI Appendix IV Summer 1976 Addenda has been performed and it was found that the newer edition is the first time that inservice inspection of installed steam generator tubing is addressed, therefore, the newer edition must be referenced to satisfy the Technical Specification surveillance requirements.
The Inservice Inspection program pertaining to steam generator tube inspection vill then be revised to comply with the newer edition, Appendix IV of ASME Section XI Summer 1976 Addenda.
Attachment E, Section 4.4.10b has been revised to provide an alternate examination schedule for the Reactor Vessel nozzle to safe end welds.
Inspections performed thus far have found no reportable defects and the alternate examination methods will provide suf ficient data to detect nozzle to safe-end defects, minimize the number of core barrel lifts that must be made and reduce the personnel radiation exposure related to this task.
The OSC and ORC have reviewed this proposed Change Request to the Technical Specifications and have determined that no unreviewed safety implications are associated with this change and that these changes do not constitute an unreviewed safety question.
In order that we may modify our refueling schedule to reflect these changes, we would appreciate your response on this request by December 15, 1981.
We have determined this to be a Class IV request, and a check for $12,300 will be sebsitted under separate cover in accordance with 10CFR 170.22.
If you have any questions regarding this response, please contact my office.
Very trulv yours, J.
. Carey Vice President - Nuclear cc: United States Nuclear Regulatory Commission Attn:
Mr. D. A. Chaney, Project Manager Operating Reactors Branch No. 1 Division of Licensing Washington, DC 20555 Mr. D. A. Beckman, Resident Inspector U. S. Nuclear Regulatory Commission Beaver Valley Power Station Shippingport, PA 15077 U. S. Nuclear Regulatory Commission c/o Docuruent Management Branch Washington, DC 20555
COMM0fMEALTH OF PENNSYLVANIA)
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COUNTY OF BEAVER
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, before On this._
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It4/4////.Jdffv2/ a Notary Public in and for said Commonwealth me, and, County, personally appeared J. J. Carey, who being duly sworn, deposed, and said that (1) he is Vice President of Duquesne Light, (2) he is duly authorized to execute and file the foregoing Submittal on behalf of said Company, and (3) the statements set forth in the Submittal are true and correct to the best of his knowledge, information and belief.
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