ML20004F610

Submits Monthly Repts for Tasks Initiated on 810417 Re NUREG-0737, Applicability of TMI Action Plan Requirements to Fort St Vrain & Htgrs, for Period Ending 810515

ML20004F610
Person / Time
Site:	Fort Saint Vrain
Issue date:	05/12/1981
From:	Ball S OAK RIDGE NATIONAL LABORATORY
To:	John Miller Office of Nuclear Reactor Regulation
References
CON-FIN-B-0762, CON-FIN-B-762, RTR-NUREG-0737, RTR-NUREG-737, TASK-***, TASK-TM NUDOCS 8106190202
Download: ML20004F610 (5)

Text

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OAK RIDGE NATIONAL LABORATORY 09tMATtO SY UNION CAR 8tDE CORPORATION NUCLEAR Olvisl0N O

POST OFFICE 80X Y oi 1E, TENNESSE E 37830 ey 12, 1981 g A' I f 6

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Mr. James R. Miller, Chief Standardization and Special Projects Branch

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h.45 h g Division of Licensing [-' CU 1,* gcAP 1 -

U.S. Nuclect Regulatory Commission T Washington, D.C. 20555 C

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'C J Daar Mr. Miller: q ,3

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Subject:

Monthly Report " Applicability of TMI Action Plan Requirements to Fort St. Vrain and HTGRs", for Period Ending May 15, 1981 (FIN NO. B0762)

Work Completed During the Reporting Period The task was initiated April 17, 1981. Each of the action plan items in NUPEG-0737 was reviewed briefly to determine its applicability to Fort St. Vrain and to HTGRs in general. Letters submitted by Public Service Co. of Colorado (PSC) responding to the Action Plan items were also reviewed briefly to determine

, areas in which .there may be some question or di'shgreement as to the applicability of the NRt. requirements. The results of this preliminary survey are given in Enclosure 1.

The survey of the Action Plan items which were considered applicable to .

Fort St. Vrain indicated that there were a number of topics for which technical <

assistance is needed from persons outside the aresent ORNL/RSR HTGR Safety Program group. Initial steps were taken to identify and enlist them. Those topics requiring outside help are identified as notad in Enclosure 1.

Discussions were held with NRR s'taff in Bethesda on April 30 to clarify the work scope requirements. Additional reference material on emergency response plan and emergency response facility requirements was obtained and reviewed.

In-depth reviews of these documents (NUREG-0654 rev. 1 and 0693) will be factored into the existing tasks per NRR request.

The work proposal (Standard Order for DOE Work) for the prog am was written and submitted. '

l Funds Spent During the Reporting Period (It should be noted that expenditures for monthly periods ending the 15th of the month cannot be reported precisely because the ORNL financial reporting system works b 810 61G G AOf the month.) 9(

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Estimated costs for manpower:

Task 1: $2900 o

Task 2: JO Computer Costs: $0 Travel Costs: $300 Problems or Delays Encountered or Anticipated None.

Plans for the Next Reporting Peri,od 1 Sources of additional technical assistance will be identified, recruited, and put to work on specific action item tasks. Selected tasks will be reviewed in depth.

Yours truly, k

S. J. sail Instrumentation & Controls Division SJB:rtw cc: Director, Division of Licensing, NRR I

R. Tedesco, Division of Licensing, NRR ,,

B. L. Grenier, NRR G. Kuraycz, NRR R. Foulds, RSR J. C. Conklin .

R. M. Harrington P. R. Kaston A. L. Lotts J. P. Sanders

.'S. J. Ball Encin ur, 1 5/12/81 NUREG-0737 Review 3 .

1. Action Plan. Items that do not apply to Fort St. Vrain or HTGRs - No plans for further review.

Item No. Title I.B.l.2 Independent Safety Engineering Group II.B.1 Reactor Coolant System Vents II.D.1 Performance Testing of Boilin3-Water Reactor and Pressurized-Water Recetor Relief and Safety Valves (NUREG-0578, Section 2.1.2)

II.D.3 Direct Indication of Relief-and Safety-Valve Position II.E.3.1 Emergency Power Supply for Pressurizer Heaters II.E.4.1 - Dedicated Hydrogen Penetrations II.G.1 Emergency Power for Pressurizer Equipment II.K.2 Orders on B&W Plants II.K.3 Final Recommendations by the B&O Task Force *

• Except for items 17,18,30, sed 31 i

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- S. J. Ball-5/12/81 .

NUREG-0737 Review

2. Action Plan Items whose applicability to Fort St. Vrain and HTGRs is m, questionable or partial - Further Review is required:

Item No. Title II.E.1.1 Auxiliary Feedwater-System Evaluation II.E.1.2 Auxiliary Feedwater System Automatic Initiation and Flaw Indication II.E.4.2 Containment Isolation Dependability II.F.1 Noble Gas Effluent Monitor II.F.2 Instrumentation for Detection of Inadequate Core Cooling II.K.3.18 Modification of Automatic Depressurization System Logic--raasibility for Increased Diversity for Some Event Sequences II.K.3.30 Revised Small-Break Loss-of-Coolant-Accident Methods to Show Compliance with 10 CFR Part 50, Appendix K

. II.K.3.31 Plant-Specific Calcuations to Show Compliance With 10 CFR Part 50.46 III.D.l.1 Integrity of Systems Outside Containment Likely to Contain Radioactive Material for Pressurized-Water i

Reactors and Boiling-Water Reactors

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5. J. Ball

5/12/81 -

NUREG-0737 Review

3. Action Plan Items that apply to Fort St. Vrain and/or HTGRs - Recommendations will be developed:

Ites No. Title Need Outside help?

I.A.1.1 Shif t Technical Advisor I.A.l.3 Shift Manning I.A.2.1 Immediate Upgrading of Reactor Operator and Senior Reactor Operator Training and Qualifications I.A.2.3 Administration of Trainiog Programs yes I.A.3.1 Revise Scope and Criteria for Licensing Examinations--

Simulation Exams I.C.1 Guidance for the Evaluation and Development of Procedures for Transients and Accidents I.C.5 Procedures for Feedback of Operating Experience to Plant Staff I.C.6 Procedures for Verifying Correct Performance of Operating Activities I.D.1 Control-Room Design Reviews yes 1.D.2 Plant Safety Parameter Display Console yes II.B.2 Design Review of Plant Shielding and yes Environmental Qualification of Equipment for Spaces /?ystems Which May Be Used In Postaccident Operations II.B.3 Postaccident Sampling Capability yes

~.8.4 Training for Mitigcting Core Damage II.K.3.17 Report on Outages of Emergency Core-Cooling Systems Licensee Report and Proposed Technical Specification Changes III . A . 2 Improving Licensee Emergency yes Preparedness--Loag-Term III.D.3.3 Improved Inplant Iodine Instrucentation yes Under Accident Conditions III.D.3.4 Control-Room Habitability Requirements

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