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MONTHYEARML20245A4481986-09-30030 September 1986 Revised Draft Conformance to Generic Ltr 83-28 Item 2.1 (Part 1) Equipment Classification Hope Creek,Peach Bottom 2 & 3,Perry 1 & 2 & Pilgrim 1 Project stage: Draft Other ML20212M5271987-03-0303 March 1987 Amend 99 to License DPR-35,revising Tech Spec Requirements for Certain Instrument Channel Test & Calibr Frequencies to Once Per Operating Cycle During Refueling Outages Project stage: Other ML20206G8031987-03-26026 March 1987 Forwards Safety Evaluation Granting Inservice Insp Program Relief Requests PRR-8 Re Surface & Volumetric Exam of RHR Sys HX Nozzles & PRR-9 Re Exam of 100% of Required Vol for nozzle-to-vessel Welds,Per Util 860415 & 1212 Ltrs Project stage: Approval ML20214Q4191987-06-0101 June 1987 Forwards Summary of Nrr/Util 870521 Meeting Re Licensing Issues for Plant.List of Attendees Also Encl Project stage: Meeting ML20207A5801987-08-0505 August 1987 Forwards SER & SALP Input Re Util 870401 Request for Exemption from 10CFR50,App R,Section Iii.J Requirement to Install 8 H Battery Powered Lighting in Outside Yard Area. Exemption Should Be Granted Project stage: Approval BECO-87-195, Submits Current Status of Improvements Being Implemented in Response to NUREG-0737,Item II.F.2 & Generic Ltr 84-23. Improvements Include Instrumentation for Reactor Water Level Sys & Installation of Analog Trip Sys1987-12-0808 December 1987 Submits Current Status of Improvements Being Implemented in Response to NUREG-0737,Item II.F.2 & Generic Ltr 84-23. Improvements Include Instrumentation for Reactor Water Level Sys & Installation of Analog Trip Sys Project stage: Other ML20237B1351987-12-10010 December 1987 Summary of 871124 Meeting W/Util & Member of Public Re Fire Protection Issues at Plant.Meeting Agenda,List of Attendees & Summary of Significant Matters Discussed Encl Project stage: Meeting ML20205F0051988-02-0505 February 1988 Discusses Resolution of Fire Protection Licensing Actions Project stage: Other ML20150C7401988-03-0808 March 1988 Provides Info Re Status of Inservice Insp & Augmented IGSCC Insp Programs for Plant 1987 Refueling Outage Project stage: Other ML20150C7641988-03-0808 March 1988 Advises That 860922 & 870506 Details of Inservice Insp & Augmented IGSCC Insp Program for 1987 Refueling Outage Meets Guidelines of Generic Ltr 84-11 & Acceptable Project stage: Other ML20207B0121988-06-0303 June 1988 Forwards SER Re Util Request for Exemption from Specific Technical Requirements of Section Iii.G of App R to 10CFR50. Exemption Should Be Granted.Salp Input Also Encl Project stage: Approval 1987-03-03
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jo UNITED STATES g
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g NUCLEAR REGULATORY COMMISSION j
WASHINGTON, D. C. 20555
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JUN 0 31988 Docket No. 50-293 MEMORANDUM FOP: Richard H. Wessman, Project Director Project Directorate I 1 Division of Reactor Pt ojects I/II Office of Nuclear Rc3ctor Regulation FROM:
Conrad E. McCracken, Chief Chemical Engineering Branch Division of r.igineering and Systems Technology Office of Nuolear Reactor Regulation
SUBJECT:
SAFETY EVALUATION REPORT CONCERNING REQUESTS FOR EXEMPTION FROM PROVISIONS OF SECTION III.G.2 0F APPENDIX R TO 10 CFR PART 50 IN CERTAIN AREAS OF THE PLANT (REQUEST N05. 15, 18 AND 22) - PILGRIM NUCLEAR POWER STATION (TAC NO. 65962) 1 Plant Name:
Pilgrim Nuclear Power Station Licensee: Boston Edison Company Docket No.:
50-293 Review Basis:
Exemption Requests - Section III.G of Appendix R to 10 CFR Part :50 Review Status: Complete Our Safety Evaluation.' aport of the licensee's requests for exemption from specific technical requirements c.1 Section III.G of Appendix R to 10 CFR Part 50 (Exemption Request Nos. 15, D and 22) in several different areas of the plant is enclosed (Enclosure 1). Our conclusion as contained in the enclosed SER is that all their requests for exemption should be granted.
After we had reviewed, and accepted, these three requests for exemption, we realized that all three could have been processed under the provisions of Generic Letter 86-10. The licensee's submittal would have satisfied the requirement to perform and maintain for later NRC review, a technical evaluation justifying the deviation from the specific requirements. You may wish to advise the licensee of this in the event they have similar deviations in the future.
6-i CONTACT:
j' O. P. Notley, DEST Ext. 20 47 -
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t' Richard H. Wessman l Our SALP input for this SER is provided in Enclosure 2.
We consider our efforts on TAC No. 65962 to be complete.
onrad E. McCracken, Chief Chemical Engiileering Branch Division of Engineering and Systems Techno.ogy-Office of Nuclear Reactor Regulation
Enclosures:
- 1.
Safety Evaluation Report 2.
SALP Input j
cc w/ enclosures:
j L. Shao J. Richardson S. Yarga B. Boger D. Mcdonald 4
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