ML19262A487
| ML19262A487 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 02/28/1972 |
| From: | Deyoung R US ATOMIC ENERGY COMMISSION (AEC) |
| To: | John Miller METROPOLITAN EDISON CO. |
| References | |
| NUDOCS 7910300429 | |
| Download: ML19262A487 (8) | |
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m AEC PDR Local PDR Nf' i Docketi DRL Rxd Reading Docket No. 50-289 PWR-2 SHHanauer FSchroeder TRWilson Metropolitan Edison Company RSBoyd Attu:
Mr. J. G. Miller RCDeYoung OCC Vice President DJSkovholt O(2)
P.O. Box 542 HRDenton ras (2)
Reading, Pennsylvania 19603 RWKlecker HSchierling EGCase ACRS (16)
Centieren:
RRMaccary PWR Branch Chiefs In our continuing review of your application to operate the Three Mile Island Nuclear Station, Unit 1, we find that additional information is needed to complete our evaluation. The enclosed requests pertain to your Final Safety Analysis Report (FSAR) and have been discussed with your repr.esentatives in a meeting held at Bethesda on January 28, 1972.
The addd.tional information requests have been categorized in groups which correspond to like numbered sections of the FSAR. Also, the request:s are numbered consecutively to our previous requests.
To maintain our review schedule we will need your complete reply by March 31,1972. Please inform us within seven (7) days after receipt of this latter as to the date you vill be able to submit the requested information to us.
Sincerely, (s)m 2
R. C. DeYoung, Assistant Director for Pressurir.ed Water P4 actors Division of Reactor Licensing
Enclosure:
Request for Additional Informationj cc: w/enci General Public Utilities Service Corporation, R. W. Heward, Project Manager, P.O. Box 1018, Reading, Pennsylvania 19603 General Public Utilities Service Corporation, J. R. Thorpe, Safety and Licensing Manager, 260 Cherry Hill Road, Parsippany, New Jersey 07054 Shaw, Pittman, Potts, Trowbridge & Madden, Attn: Mr. Gerald Charnoff, Esq., 910 - 17th Street, NW, Wahington, D. C. 20006 .DRL1WR-2,4.h, P DRL:BWR-2 DRL:ADg,s,, cmcr> HSchierling KKniel RCD 'u $URNAME > .[ DATE > ..I. Form AEC-Ste (Rev. 9-5h AECM 0240
- v. s. GOVERNME:NT PRDiTM OFFICE : 1970 0 - 405-344 7910300 % %
,[ +, UNITED STATES ff N ATOMIC ENERGY COMMISSION 'J, if. ' I WASHINGTON. O.C. 20545 February 28, 1972 Docket No. 50-289 Metropolitan Edison Company Attn: Mr, J. G. Miller Vice President P.O. Box 542 Reading, Pennsylvania 19603 Centlemen: In our continuing review of your application to operate the Three Mile Island Nuclear Station, Unit 1, we find that additional information is needed to complete our evaluation. The enclosed requests pertain to your Final Safety Analysis Report (FSAR) and have been discussed with your representatives in a meeting held at Bethesda on January 28, 1972. The additional information requests have been categorized in groups which correspond to like numbered sections of the FSAR. Also, the requests are numbered consecutively to our previous requests. To maintain our review schedule we will need your complete reply by March 31, 1972. Please inform us within seven (7) days after receipt of this letter as to the date you will be able to submit the requested information to us. Sincerely, a -v R. C. DeYo* g, As stant Director for Pressurized Water Reactors Division of Reactor Licensing
Enclosure:
Request for Additional Information ec: w/enci General Public Utilities Service Corporation, R. W. Heward, Project Manager, P.O. Box 1018, Reading, Pennsylvania 19603 Ceneral Public Utilities Service Corporation, J. R. Thorpe, Safety and Licensing Manager, 260 Cherry Hill Road, Parsippany, New Jersey 07054 Shaw, Pittman, Potts, Trowbridge & Madden, Attn: Mr. Gerald Charaoff, Esq., 910 - 17th Street, NW, Washington, D. C. 20006 1486 332
REQUEST FOR ADDITIONAL INFORMATION METROPOLITAN EDISON COMPANY THREE MILE ISLAND UNITS 1 AND 2 (DOCKET NO. 50-289) 12.0 CONDUCT OF OPERATIONS 12.3 Provide additional information concerning the corporate technical support organization that will specifically support the operation of the nuclear plant. Include a description of the duties, responsibilities, and authority of the Superintendent of Production and the assigned engineering technical staff. Provide information concerning the qualifications, educational backgrounds, and experience of the corporate technical support staff (Ref erence ANSI-N18.1). 12.4 Provide resumes of all key supervisory personnel including qualifcations, educational backgrounds and experience, and specific nuclear training. These include the Station Superintendent, Supervisor of Operations, Supervisor of Maintenance, Station Engineer, Control and Instrument Foreman, the five Shift Foremen, Nuclear Engineer, Radiation Protection Supervisor, and Chemical Supervisor. 12.5 Provide a description of the function, responsibility, and authority of the Control and Instrument Foreman. This is considered a key supervisory positica (See ANSI-N18.1). 12.6 Describe the duties and the authority of the Station Engineer, Nuclear Engineer, and Chemical Supervisor. 12.7 Designate on Figure 12.1 the key supervisory personnel for whom minimum qualifications are specified in the Technical Specifications. 12.8 Describe the specific succession of responsibility sof supervisory personnel for overall operation of the facility in the event of absences or emergencies. 12.9 Des; ribe the functions and responsibilities of unlicensed operators and technicians. 12.10 Provide additional 1, formation concerning the training program. This information should include: a. A detailed description of the nuclear training program for the plant non-supervisory personnel, including both formal and on-the-j ob training. Give the duration of each aspect of the program ( ANSI-N18.1). b. A description of the general employee training given to all personnel regularly employed at the nuclear plant.
. c. Designation of the individual responsible for the administration and evaluation of the training program, d. A detailed description of the provisions made for replacement and retraining. Is the use of a plant simulator anticipated? A description of the training provided for those offsite organizations e. that may be called upon to assist plant staff during an emergency. 12.11 Describe the provisions made for maintaining records of qualifications, experience, training, and retraining of each member of the plant staff. 12.12 Provide a description of the written agreements with offsite organizations for emergency assistance. 12.13 Has the emergency planning program considered emergencies other than those listed e.g., natural disasters, transporation accidents, and sabotage? 12.14 Who will evaluate onsite and offsite radiation levels following an accident? What predetermined action levels have been developed for implementation of protective measures? What recommendations will be made to local authorities for evacuation, take cover, or other protective measures for various action levels? 12.15 Provide a detailed description of the membership of the Emergency Planning Group. 12.16 Provide additional information discussing the allowance req ested for use of protective clothing and equipment (Reference 10 CFR 20.103(c)(3)). bb
. Appendix 12A RADIATION _ EMERGENCY PLAN 12Al Specify the location of the emergency monitoring kits. 12A2 The responsibilities and duties of the Station Superintendent and the Station Engineer appear to conflict with the Emergency Operating Organization in Figure 12A-3. The Station Engineer " supervises and coordinates the execution of the Radiu: ion Emergency Plan", but the Superintendent heads the emergency organization and also has the responsibility for coordinating the plan. 12A3 Provide a list of the designated alternates for the Station Super-intendent, the Supervisor of Operations, and the Station Engineer during a radiation emergency. 12A4 Explain the rationale of not declaring a general emergency en the occurrence of a major accident which could potentially result in the release of radioactive material to the environment. The basis for requesting offsite support shall be in accordance with 10 CFR 20.105. 12A5 Discuss the meaning of " periodically" with regard to the review and revision of the Radiation Emergene.y Plan. Discuss how the holders of the Radiation Emergency Plan are assured that they have the latest revision of the plan. 12A6 Discuss the frequency at which training, retraining, and drills of the emergency plan will be held. What provisions have been made for training offsite personnel from organizations who might provide emergency assistance? 12A7 The recovery and reentry section is inadequate. Expand this section to include such matters as: exposure guides for rescue personnel, the determination of the accessibility of plan areas following an cccident, the availability of current operating records, the storage of building plans, procedures, and other essential information in a location readily accessible in an emergency, interviewing evacuated employees to obtain information about the emergency, and the designation of a technical group to determine reentry advisability. 86 335
. 13.0 INITIA!. TESTS AND OPERATION 13.1 Provide addicional information with regard to the Test Working Group. This information should include a description of the membership with the qualifcations of the individual members, a description of the responsibility, authority and function of the group, and a description of its interrelationship with the General Of fice Review Board. 13.2 Provide detailed information and discussions wir *2 gard to the extent to which your program will comply with the suggescions in the following two references: " Guide for the Planning of Preoperational Testing Programs", a. U.S. Atomic Energy Commission, December 7,1970. b. " Guide for the Planning of Initial Startup Programs", U.S. Atomic Energy Commission, December 7,1970. 1486 336
.. 15.0 TECHNICAL SPECIFICATIONS 15.6 Administrative Controls 15.6.1 Provide justification for excluding from the definition of abnormal occurrences the following statements: " Observed inadequancies in the implementation of administrative or procedural controls such that the inadequacy causes or threatens to cause the existence or development of an unsafe condition in connnection with the operation of the plant," and " Conditions arising from natural or offsite man-made events that affect or threaten to affect the safe operation or the plant." Subsection 15.6.3 uses the ANS 3.2 definition. 15.6.2 In Section 15.1.2 the definition "c" of the abnormal occurrence is limited to a radioactive release from the site. Discuss why releases f rom any plant system acting as a boundary are excluded (Reference proposed standard ANS 3.2, draf t 6 dated September 8,1971). 15.6.3 Justify the provision for the requiremant of only one licensed control room operator during norma: operations as specified as a footnote on page 15-95. This disagrees with Figure 12.1 which specifies 10 licensed reactor control room operators for the 5 shif ts. 15.6.4 Describe the provisions ter health physics coverage on each shift. 15.6.5 For Specification F of subsection 15.6.1, list the positions by title that are referred to (See ANSI-N18.1). 15.6.6 Provide a copy of the written charter for both the Plant Operations Review Committee and the General Office Review Board. Include, as a minimum, the provisions listed in Section 4 of ANS 3.2. 15.6.7 Provide the basis for establishing less than a maj o rity of the Plant Operations Review Committee as a quorum. 15.6.8 For the General Office Review Board, identify by title and list the technical specialty and experience of each member. Designate the Chairman and Vice Chairman. 15.6.6 Explain the omission of the following responsibilities of the Board: a. Review of tests and experiments and their results, which may constitute an unreviewed safety hazard. b. Review of significant operating abnormalities or deviations from normal and expected performance of plant equipment. 15.6. 10 It appears from Figure 15.6.1-1 that the General Public Utilities Nuclear Power Activities Group provides the corporate technical support for the plant. If so, provide a list of the assigned engineering technical staff, their qualifications, educational background and experience, and their responsibility and authority over plant operations (See request 12.1). If outside consultants are used for technical support for plant operations, specify areas of responsibility and functional working arrangements.
a. 15.6.11 The listing of the detailed procedures in subsection 15.6.2, Specification A is not complete. For example, procedures for surveillance and testing and plant emergencies are not included. Provide a complete list of the types of procedures to be used for plant cperations. 15.6.12 Specify the frequency of review of operating procedures and emergency procedures by operating personnel. 15.6.13 Discuss how " temporary" minor changes in procedures, approved by the Shif t Foreman, will be reviewed and approved by the Station Superintendent or the Plant Operations Review Committee. 15.6.24 Discuss the specific responsibility of the General Of fice Review Board with regard to the review and approval (with appropriate recommendations) of reports of abnormal occurrences and of exceeding a safety limit (subsections 15.6.3 and 15.6.4). 15.6.15 Describe the system for the revision of plant operating, maintenance, testing, and emergency procedures. 15.6.16 The specification under subsection 15.6.5 does not include such items as fuel exposure, shutdowns, fuel inventories and transfers, minutes of meetings of review and audit groups, and reactor coolant system inservice inspections. Provide a complete listing of the s station logs and records to be retained, with a retention period given for each. 15.6.17 Provide justification for the proposed exception to the 10 CFR 20 regulation regarding the control of access to high radiat: m. areas. 15.6.18 Discuss how the written reports submitt.ed to the AEC per Specification B of subsection 15.6.7 will include: (a) an outline of the measures taken to assure that the cause of the incident has been determined, and (b) a discussion of the incident as it relates to similar incidents. 15.6.19 Subsection 15.6.7 does not include the provision for a startup report and a first year operations report. The subsection does not address the following events that should be reported within 30 days: inadequacy in the implementation of administrative or procedural controls, conditions involving a possible single failure, occurrences or conditions involving an offsite threat to the safety of operation of the facility, and any substantial variance from performance specificaticas. Specify what "other information" will be included in the operations summary of the 6-month reports, e.g., procedure changes and results of tests and inspections (Sae Safety Guide 16). Include under shutdown, information as to plant status during outage, and corrective action taken to prevent repetition, if appropriate. Expand the maintenance and facility changes paragraphs using Safety Guide 16 as guidance. Include a designation of the destination of waste shipments. Elaborate on what is meant by "A summary of results", under Environmental Monitoring. Does this include the highest, lowest, and average concentrations or levels of radiation for the sampling point, and the number of locations at which levels are found to be significantly above local background? 1486 338}}