ML19343D241
| ML19343D241 | |
| Person / Time | |
|---|---|
| Site: | Point Beach, Arkansas Nuclear, Prairie Island  |
| Issue date: | 04/27/1981 |
| From: | Martin R Office of Nuclear Reactor Regulation |
| To: | Chaney D Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8105040031 | |
| Download: ML19343D241 (3) | |
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MEMORANDUM FOR: Dennis A. Chaney,. Project Manager Operating Reactors Branch #1, DL
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Robert E. Martin, Project Manager Operating Reactors Branch #3, DL
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SUBJECT:
INSERVICE INSPECTION AND TESTING (ISI/IST) y This is in response to Mr. Chaney's memo of April 14, 1981 on this subject, for the Prairie Island 1 & 2 plants, and the ANO-2 plant.
Prairie Island 1 & 2 (PI h & 3-), TACS 11429 ISI Amendments to the licenses issued November 14, 1980, replaced the former ISI Program with one that was reviewed with respect to 10 CFR 50.55a.
These amendments also addressed the granting of relief from certain require-ments of ASME Code Section XI pursuant to 50.55a. This takes care of ISI for Prairie Island until the next 120 month interval begins which is 12/16/83 for Unit 1 and 12/21/84 for Unit 2.
NSP will submit their updated program and requested relief three months prior to those dates. Therefore, it appears that the review status for PI 1 & 2 ISI should be updated to "F-Action Complete" on your status list. A copy of the 11/14/80 amendment is attached.
IST This IST program for PI 1 & 2 is still being done pursuant to Technical Specifications and the NRC letters of September 17, 1977 and May 19, 1978 which granted interim relief from ASME code requirements.
There is a need to clean this situation up by reviewing the IST program for pumps and valves and associated requests for relie^ so that IST may also be measured against the requirements of the applicable ASME Code.
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I will participate in whatever way I ca'n to get a review of IST completed for PI 1 & 2.
The licensee is eager to support such a review since they i
are interested in getting this sometimes confusing situation reviewed and approved.
I have certain information which you may need in acting on this which includes-(1) the submittals describing the PI IST and the requested relief items (about 6 documents), and (2) a draft version of an SER developed by PNL about May 1979.
If you currently have an SER in preparation as your status list indicates please provide me a copy. If that status list's SER is the same one as the May 79 PNL SER, then we should decide whether (a) we can go back to PNL for technical resources to finish the review. This would appear to be attractive since I understand the same people who did the earlier PI work are still at PNL and hopefully would have less startup tine in the review; or (b) do we use the May 79 draft as an information source only and review IST from the beginning Please advise me of MEB's plans on PI.
If we could go back to PNL, we could probably get IST for PI completely resolved and issued within six to nine months.
Arkansas Nuclear One - Unit 2 (ANO-2), TACS 12062 ANO-2 was licensed in 1978 and their IST plan is in accordance with Section XI as specified by Technical Specification 4.0.5.
1.
By letter dated June 15, 1978, they requested relief on certain items.
2.
By letter dated Septembe-21; 1979, we granted them the requested relief, on an interim basis, pending completion of our detailed review of their request.
3.
We contracted with INEL to review the ANO-2 requests and on February 21, 1980, we sent AP&LCo a list of questions developed by INEL. A copy is attached.
4.
By letter dated October 29, 1980, AP&LCo i iponded to the INEL questions.
A copy is attached.
o Where does this leave us on ANO-2 at this time? Can we have INEL review the 10/29/80 responses and write an SER?. ANO-2 is not included on your status list and apparently it should be. Please advise.
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' Robert E. Martin, Project Manager Operating Reactors Branch #3 Division of Licensing Encle res:
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License Amendment issued 11/14/80 for PI 2.
Letter NRC to AP&L Co dated 2/21/80 on IST 3/ Letter AP&L Co to NRC dated 10/29/80 on IST a
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November 14, 1980 Docket Nos. 50-282 and 50-306 Mr. L..O. Mayer, Manager Nuclear Support Services Northern States Power Company 414 Nicollet Mall - 8th Floor Minneapolis, Minnesota 55401
Dear Mr. Mayer:
The Conwission has issued the enclosed Amendment No. 43 to Facility Operating License No. OPR-42 and Amendment No. 37 to Facility Operating License No. OPR-60 for the Prairie Island Nuclear Generating Plant. The amendments consist of changes to the Technical Specifications in response to your application transmitted by letters dated October 15, 1976 for Unit No.1 and October 12, 1977 for Unit No. 2.
This amendment revises the Technical Specifications for both Units 1 and 2 by replacing the current inservice inspection Technical Specifications with an inservice inspection program that meets the requirements of 10 t.FR 50.55a. The issuance of these amendments and revision of the Tech-nical Specifications supersedes the relief from the ASME code inservice inspection requirements provided in our letters of September 17, 1977 for Unit No.1 and May 19, 1978 for Unit No. 2.
Relief from certain inservice inspection requirements is hereby' granted as discussed in the enclosed Safety Evaluation. We have determined that the granting of this relief is authorized by law and will not endanger life or property or the comon defense and security and is otherwise in the public interest. This relief is granted, except for certain require-ments as discussed in the Safety Evaluation, in response to your request of February 1,1978, as revised by your letters dated September 15, 1978, June 8, 1979, September 19,1979, April 17,1980 and September 3, 1980.
A copy of the Safety Evaluation and the Notice of Issuance are also enclosed.
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-Q Robert A. ' Clark, Chief Operating Reactors Branch #3 Division of Licensing Enclosures and ces:
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Mr.'L.' O. Mayer 2,
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Enclosures:
1.
Amendment No. 43 to DPR-42 2.
Amendnent No. 37 to DPR-60 3.
Safety Evaluation 4.
Notice of Issuance cc w/ enclosures:
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l Mr. L. O. Mayer Northern States Power Cospany cc: Gerald Charnoff, Esquire Mr. John C. Davidson, Chairman Shaw, Pittmen, Potts and Trowbridge Goodhue County Board of Comissioners 1800 M Street, N.W.
321 West Third Street Washington, D. C.
20036 Red Wi,ng, Minnesota 55066
. Ms. Terry Hoffman Bernadd M. Cranum Executive Director Bureau of Indian Affairs, DOI Minnesota Pollution Control Agency 831 Second Avenue South 1935 W. County Road 82 Minneapolis, Minnesota 55402 Roseville, Minnesota 55113 Director, Technical Assessment Divisi The E,nvironmental Conservation Library Office of Radiation Programs (AW-459)
Minneapolis Public Library
,U. S. Environmental Protection Agency 300 Nicollet Mall Crystal Mall #2 Minneapolis, Minnesota 55401 Arlington, Virginia 20460 Mr. F. P. Tierney, Plant Manager U. 5. Environmental Protection Agency Prairie Island Nucleat Generating Plant Federal Activities Branch Northern States Po~wer Cocpany Region V Office Route 2
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ATTN: EIS COORDINATOR Welch, Minnesota 55089 230 South Dearborn Street Chicago, Illinois 60604 Joclyn F. Olson, Esquire Special Assistant Attorney General ccw/ enclosures (s)andin' coming
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Minnesota Pollution Control Agency
. dtd: 10/15/76 In 10/12/77 1935 W. County Road B2 Chairman, Public Service Comission Roseville, Minnesota 55113 of Wisconsin Robert (. Nybo, Jr., Chair: nan Hill Far=s State Office Building Madison, Wisconsin 53702 Min'1esota-Wisconsin Scundary Area Concission 619 Second Street Hudson, Wisconsin 54016 ij.S.Nuclair~Regulato'rCocnission Resident Inspectors Office Route f2, Box 500A.
Welch, Minnesota 55089 l
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NORTHERN STATES POWER COMPANY DOCKET NO. 50-282 PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 43 License No. OPR a2 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Northern States Power Company (the licensee) dated October 15, 1976 as supplemented by letter dated February 1; 1978 and revised September 15,1978, June 8, 1979, April 17,1980 an.1 September 3,1980, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set, forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There,is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inbaical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-42 is hereby amended to read as follows:
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 43 T0 FACILITY OPERATING LICENSE NO. DPR-42 AND AMENDf1ENT NO. 37 TO FACILITY OPERATING LICEi!SE NO. DPR-60 NORTHERN STATES POWER COMPANY PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNIT NOS. 1 AND 2 DOCKET NOS. 50-282 AND 50-306 By application transmitted by letter dated October 15, 1976 for Unit 1 and October 12, 1977 for Unit 2, the Northern States Power Company (the licensee) requested changes to the Technical Specifications (TS) appa.nded to Facility Operating License Nos. DPR:42.and DPR-60 for the Prairie Island Nuclear Generating Plant Unit Nos.1 and 2, respectively. The proposed change
'would remove the specific inservice inspection requirements from the TS and replace them with the Prairie Island Nuclear Generating Plant Inservice Inspection Program.
As required by 10 CFR 50.55a(g), the Northern. States Power Company has updated the Inservice Inspection Program for the Prairie Island Nuclear Generating Plant Unit Nos. I and 2 facility to the requirements of the 1974 Edition through Sumer 1975 Addenda of Section XI ASME Boiler and Pressure Vessel Code.
Based on information submitted by letters dated February 1, 1978, September 15, 1978, June 3, 1979, September 19,1979, April 17,1980 and September 3,1980, it has been determined that certain requirements of the Code cannot be implemented at the facility because of component or system design, geometry, or materials of construction. Requested relief from those requirements has been evaluated and our determinations to grant or deny the requests are documented below.
INSERVICE INSPECTION I.
CLASS I C0ftPONENTS A.
Ucits 1 and 2
~t when exam? quest relief from having a calibration standard of the correct length 1.
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ning reactor vessel closure head studs.
Code Reauirement hMENGhi@iMMMIfTQ tandard shall be as described in
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7590-01 UNITED STATES NUCLEAR REGULATORY COMMISSION DOCKETSN05.50-282ANd50-306 NORTHERN STATES POWER COMPANY NOTICE OF ISSUANCE 0F AMENDMENTS TO FACILITY OPERATING LICENSES The U. S. Nuclear Regulatory Comission (the Comission) has issued Amendment No.43 to facility operating license No. OPR-42, and Amendment No. 37 to Facility Operating License No. DPR-60 issued to Northern States Power Company (the licensee), which revised Technical Specifications for operation of Prairie IslandJuclear Generating Plant, Units Nos.1 and 2 (the facilities) located in Goodhue County, Minnesota. The amendments are effective as of the date of issuance.
The amendments revise the Technical Specifications to replace the current inservice inspection Technical Specifications with an inservice inspection program that meets the requirements of 10 CFR 50.55a.
By letter dated November 14,1980 as supported by the related safety evaluation, the Commission has also grsnted relief from certain requirements of the ASME Code,Section XI, " Rules for 7 arvice Inspection of Nuclear Power Plant Components" to the licensee. The relief relates to the inservice inspection program for the facilities. The ASME Code requirements are incorporated by reference into thei Commission's rules and regulations in i
The relief is effective as of its date of issuance.
The applications for the amendments and request for relief comply with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations. The Commission has
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2-made appropriate findings as required by the Act and the Comission's rules and regulaticns in 10 CFR Chapter I, which are set forth in the license amend-ments, and letter and safety evaluation granting relief. Prior public notice of the amendments was not required since the amendments do not involve a significant hazards consideration.
The Comission has determined that the issuance of these amendments and the granting of this relief will not result in any significant envir-onmental impact and that pursuant to 10 CFR 151.5(d)(4) an environmental impact statement or negative declaration and environmental impact appraisal need not be prepared in connection with issuance of this action.
For further details with respect to this action, see (1) the applica-tions for amendments dated September 15, 1976 for Unit 1 and October 12, 1977 for Unit 2, the licensee's submittals dated February 1,1978, September 15, 1978, June 8,1979, September 19,1979, April 17,1980 and Seppember 3, 1980,-
(?\\ Amendment tios. 43 and 37 to License Nos. DPR-42 and DPR-60, and (3) the Commission's related Safety Evaluation. All of these items are available for public inspection at the Commission's Public D1cument Room,1717 H Street, N. W., Washington, D. C. and at the Environmental Conservation Library, 300 4
Nicollet Mall, Minneapolis, Minnesota 55401. A copy of items (2) and (3) may be obtained upon request addressed to the U. S. Nuclear Regulatory Comission, Washington, D. C.
2055:3, Attention: Director, Division of Licensing.
Dated at Bethesda,. Maryland this 14th day of November,1980.
FOR THE NUCLEAR REGULATORY C0ffilSSION 0
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February 21, 1980 Decicet No. 50-368 Mr. William Cavanaugh, III Vice President, Generation and Construction Arkansas Power & Light Company P. O. Box 551 Little Rock, Arkansas 72203
Dear Mr. Cavanaugh:
This is to confirm the schedule for our meeting with your staff for the review of the Inservice Testing Program for Arkansas Nuclear One, Unit No. 2.
Our staff and consultants identified in Enclosure 1 will be meeting at Arkansas Nuclear One, Unit No 2 with Mr. David Mardis, Mr. Chris Shively, Mr. William Hinton and other members of your staff on March 11 and 12,1980, beginning at 8:30 a.m. each day.
. contains coments, questions and concerns about your Inservice Testing Program which will be discussed during this meeting.
Sincerely, b4 I'
hobertW.Reid, Chief Operating Reactors Branch #4 Division of Operating Reactors
Enclosures:
1.
Meeting Attendees 2.
Questions & Coments Re: Inservice Testing Program cc w/ enclosures:
See next page
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j October 29, 1980 2-100-18 Director of Nuclear Reactor Regulation ATTN:
Mr. Robert A. Clark, Chief Operating Reactors Branch #3 Divi.sion of Licensing Ul S. Nuclear Regulatory Commission Washington, D. C.
20555
Subject:
Arkansas Nuclear One - Unit 2 Docket No. 50-368 License No. NPF-6 In-Service Testing Program (File:
2-3065)
Gentlemen:
By letter dated February 21, 1980, NRC staff concerns, questions, and comments regarding the In-Service Testing (IST) program for Arkansas Nuclear One - Unit 2 were provided to AP&L. On March 11, 1980 a meeting was held between AP&L staff and NRC staff and consultar.% to discuss the information contained in your February 21, 1980, lettir.
After reviewing the February 21, 1980, letter and notes from tha aeet-ing, AP&L hereby provides, as an attachment to this letter, re'ponses to the NRC concerns and questions regarding the ANO-2 IST pro am.
Very truly yours,
.b W c m David C. Trimble Manager, Licensing DCT: MAS:skm Atta ent f{
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