Letter Sequence Request |
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Results
Other: ML19309G763, ML19316B066, ML19318A386, ML19321A701, ML19331B518, ML19331B520, ML19331B521, ML19331B586, ML19339C014, ML20010G014, ML20028A734
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MONTHYEARML19296C8241980-02-26026 February 1980
Forwards Description of Tests & Insps to Be Conducted During Outage Scheduled to Begin 800229,as Required by 791130 Confirmatory Order for Mod of License.Graphs & Svc List Encl
Project stage: Request
ML19309A7411980-03-28028 March 1980
Submits Results of Steam Generator Insp,Requested in 791130 Order.Requests Written Concurrence That Tests Are Acceptable So That Unit May Be Returned to Svc.List of Tubes Plugged & Description of QA Program Encl
Project stage: Request
ML19305D6401980-03-28028 March 1980
Circular Ltr to All Power Reactor Applicants & Licensees Re Qualifications of Reactor Operators.Forwards Revised Criteria to Be Used in Reactor Operator Training & Licensing Evaluation Under Current Regulations.W/Certificate of Svc
Project stage: Approval
ML19309G7631980-05-0202 May 1980
Forwards Response to NRC ,Addressing Remaining Items Re Implementation of Category a Lessons Learned Task Force Requirements.Administrative Controls for Five Sys Implemented.Procedures Modified
Project stage: Other
ML19316B0661980-06-0404 June 1980
Requests Concurrence That Operating Training Program Is Equivalent to Extra Man Concept or Background Studies to Justify Arbitrary Requirement.Reply Requested by 800701
Project stage: Other
ML19310A3591980-06-0404 June 1980
Advises That Util Is Forwarding,Under Separate Cover,Set of Piping & Instrumentation Diagrams for Plant.Listing of Diagrams Also Forwarded W/Package
Project stage: Request
ML19318A3861980-06-11011 June 1980
Forwards Response to NRC Re Five Addl TMI-2 Related Requirements for Operating Reactors.Assumes That Implementation of Addl Requirements Was Not Meant to Impede Completion of Previous Commitments
Project stage: Other
ML19321A7011980-07-0808 July 1980
Responds to 800604 Request for Info Re Requirement That Operator & Senior Operator License Applicants Spend 3 Months on-shift in Training.Variance to Requirement Cannot Be Permitted
Project stage: Other
ML19331B5211980-07-30030 July 1980
Control Operator Training Program, Revision 1
Project stage: Other
ML19331B5201980-07-30030 July 1980
Amended Licensed Operator Requalification Program, Revision 1
Project stage: Other
ML19331B5861980-08-0707 August 1980
Clarifies Util Re Problems in Qualifying Reactor Operators to Latest NRC Requirements.Requests Relief from Extra Man on Shift Qualification Requirement for Auxiliary Operator in Control Operator Trainee Position
Project stage: Other
ML19331B5181980-08-0707 August 1980
Forwards 800730, Amended Licensed Operator Requalification Program, Revision 1 & Control Operator Training Program, Revision 1
Project stage: Other
ML19339C0141980-10-28028 October 1980
Responds to Util Relaying Procedures for Selection & Training of Senior Operators.Conformance W/Item A.2. of NRC Cannot Be Deferred
Project stage: Other
ML19347C9921981-03-0404 March 1981
Discusses NUREG-0737 Schedule Requirements Provided in Licensee ,In Response to NRC Request for Clarification Re Accident Monitoring,Training for Mitigating Core Damage & Reactor Vessel Level Sys
Project stage: Request
ML20010G0141981-09-0808 September 1981
Forwards B&W Rept Auxiliary Feedwater Sys & 36 Oversize Drawings,Per 810703 Commitment to Submit Final Design Info Re NUREG-0737,Items II.K.2.10 & II.E.1.2.Aperture Cards Are Available in PDR
Project stage: Other
ML20028A7341982-08-17017 August 1982
Improvements in Training & Requalification Programs as Required by TMI Action Items 1.A.2.1 & II.B.4 for Point Beach Nuclear Plant,Units 1 & 2, Technical Evaluation Rept
Project stage: Other
1980-06-04
[Table View] |
Discusses NUREG-0737 Schedule Requirements Provided in Licensee ,In Response to NRC Request for Clarification Re Accident Monitoring,Training for Mitigating Core Damage & Reactor Vessel Level Sys| ML19347C992 |
| Person / Time |
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| Site: |
Point Beach  |
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| Issue date: |
03/04/1981 |
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| From: |
Fay C
WISCONSIN ELECTRIC POWER CO. |
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| To: |
Clark R, Harold Denton
Office of Nuclear Reactor Regulation |
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| References |
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| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.B.4, TASK-2.F.1, TASK-2.K.3.27, TASK-TM TAC-44188, TAC-44189, TAC-44538, TAC-44539, NUDOCS 8103100470 |
| Download: ML19347C992 (2) |
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Text
l O'
O Wnconsin Electnc ecw ccer 231 'f. M:CHIGAN, P.O. BOX 2046. VILWAUKEE. M 53201 March 4, 1981 ft-s50/. g Mr.
H.
R.
Denton, Director b([gr.[p Office of Nuclear Reactor Regulation
[
U.
S. NUCLEAR REGULATORY COMMISSION N
[y '4U /
Washington, D.
C.
20555 Attentir.-
Mr.
R. A. Clark, Chief hJS6fg-11 Operating Reactor Branch #3
N s
DOCKET NOS. 50-266 AND 50-301 N
NUREG-0737 SCHEDULE REQUIREMENTS POINT BEACH NUCLEAP PLANT, UNITS 1 AND 2 Mr. Colburn of your staff called Wisconsin Electric on february 20 with a number of inquiries regarding cur letter dated Dece:tber 23, 1980 which presented the NUREG-0737 schedule requirements as related to Point Beach Nuclear Plant, Units 1 and 2.
He first advised that the Nuclear Regulatory Commission is considering any information received by March 31 as having met the January 1, 1981 schedule date.
In this light, Mr. Colburn asked that we re-examine several of the commitment.s we made in our December 23 letter, and notify the NRC if the commitnents could be changed to meet the March 31 date.
The specific items mentioned by Mr. Colburn together with our comments or revised commitments are presented below.
The first item is identified as' Item II.F.1, Accident Monitoring. to the October 30, 1980 letter which forwarded NUREG-0737 directed that licensees inform the NRC of any exceptions or deviations from the NRC requirements and clarification ir. their sampling and monitoring plans.
This report was supposed to be submitted by January 1, 1981.
We have identified several exceptions to the NRC clarifications and will submit our discussion of these exceptions before March 31.
Item II.B.4 concerns training for mitigating core damage.
In our December 23 letter, we advised that we would be unable to initiate this training by the April 1, 1981 schedule date but that we would complete the training before the October 1, 1981 schedule date.
A generic training program for mitigating core damage has been initiated.
Our training program development will be completed by March 31, and training will be completed by October 1.
8108100 0 0
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d
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2
'i Mr. H. R. Denton March 4, 1981 t
Item II.F.2.3 discusses the reactor vessel level system.
We committed in our December 23 letter to provide a report detailing the_ planned instrumentation for monitoring of inadequate core cooling by April 1, 1981.
We hereby revise that commitment to providing the report by March 31.
Mr. Colburn also discussed Wisconsin Electric's present commitments regarding relief valve, safety valve, and block valve testing as identified by Item II.D.l.
Our commitments on these
]
items were discussed in our December 23 letter and have not changed.
We trust this letter has clarified for you any questions regarding our NUREG-0737 implementation.
If you should have any t
additional questions, please call again.
very truly yours, 1
C. W.
Fay, Director I
Nuclear Power Department 4
' Copy to NRC' Resident Inspector 1
i.
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