ML20058A680
| ML20058A680 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 06/18/1982 |
| From: | Snyder B Office of Nuclear Reactor Regulation |
| To: | J. J. Barton GENERAL PUBLIC UTILITIES CORP. |
| References | |
| NUDOCS 8207150184 | |
| Download: ML20058A680 (2) | |
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Dock;t No.L50-320 ACRS (16)
PDR OPA LPDR SECY UUN I 81982 TMI Site R/F Olynch TMIPO R/F RWeller LBarrett BWeiss Docket No. 50-320 BJSnyder TPoindexter HRDenton Service List EGCase DCS RHartfield, MPA "9
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fFas Mr. John J. Barton o
Acting Director of TMI-2 RConte GPU Nuclear Corporation RBellamy P.O. Box 400 LChandler, F! 9 Middletown, PA 17057 I&E (3)
TBarnhart (4)
Dear Mr. Barton:
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The Nuclear Regulatory Commission has issued the enclosed Amendment of Order for the Three Mile Island Nuclear Station, Unit 2 This Amendment of Order changes the sup. vvisory authority under which THI-2 Radiological Control Technicians training currently falls in Appendix A of the Tech-nical Specifications, as imposed by the Order of the Director of the Office of Nuclear Reactor Regulation on February 11, 1980. These changes are being made in response to your request of March 5,1982. This Amend-ment of Order is effective upon issuance.
Copies of the revised pages for the proposed Technical Specifications and the related Safety Evaluation are enclosed.
Sincerely.
/s/
Bernard J. Snyder, Program Director Three Mile Island Program Office l
l Office of Nuclear Reactor Regulation l
Enclosures:
As stated cc w/ encl.
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See next page l
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NRC FORM 318 (10-80) Nacu om OFFIClAL RECORD COPY usa m m -ass-m,
U-UNITED STATE 3 0F A14 ERICA NUCLEAR REGULATORY COMMISSION Dr. Judith H. Johnsrud John F. Wolf, Esq., Chairman,
. Environmental Coalition on Administrative Judge Nuclear Pcwer 3409 Shecherd Street 433 Orlando Avenue '--
Chsvy Chase, MD 2001E State College, PA 16801 Dr. Oscar H. Paris, Acministrative George F. Trewbridge, Ec.
Judge Atomic Safety and Licensing Scard Panei Shaw, Pittaan, Pctts anc Trewbridge U.S. Nuclear Regulatory Comission 1800 M. Street, N.W.
Washington, D.C.
20555" l
Mr. Frederick J. Shon, Administrative At:mic Safety and Licensing Scard Judge Panel Atcmic Safety and Licensing Scard ?anel U.S. Nuclear Regulatory C:missien l
U.S. Nuclear Regulatory Comissicn Washington, D.C.
20555" Washington, 0.C.
20555*
At:mic Safety and Licensing Acceal Xarin W. Car.er Fanel Assistan: A:: rney General U.S. Nuclear Regula:Ory C:missicn 505 E.tecutive Mousa Washingt:n, D.C.
20555" P. O. Box 2257 l
Harris:urg, FA 17120 Secn tary U.S. Nuclear :.eguia::ry ^:=is:icn i
Mr. William A. L enstat ATU:
Chief, "Tecketing i Servica 5
'19 E. Aaron Drive Wasning::n, E. ^.
2C555" 5:2:a C i1ege, ?A 15501
t UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION In the Matter of
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METROPOLITAN EDISON COMPANY, et. _al. )
Docket No. 50-320 OLA
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(Three Mile Island Nuclear Station,
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Unit 2)
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AMENDMENT OF ORDER I.
GPU Nuclear Corporation, Metropolitan Edison Company, Jersey Central Power and Light Company and Pennsylvania Electric Company (collectively, the Licensee) are the holders of Facility Operating License No. DPR-73, which had authorized operation of the Three Mile Island Nuclear Station, Unit 2 (TMI-2) at power levels up to 2772 megawatts thermal.
The facility, which is located in Londonderry Township, Dauphin County, Pennsylvania, is a pressurized water reactor previously used for the commercial generation of electricity.
By Order for Modification of License, dated July 20, 1979, the Licensee's authority to operate the facility was suspended and the Licensee's authority was limited to maintenance of the facility in the present shutdown cooling mode (44 Fed. Reg. 45271).
By further Order of the Director, Office of Nuclear Reactor Regulation, dated February 11, 1980, a new set of formal license requirements was imposed to reflect the post-accident condition of the facility and to assure the continued maintenance of the current safe, stable, long-term cooling condition of the facility (25 Fed. Reg.11282).
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-2 Although these requirements were imposed on the licensee by an Order of the Director of Nuclear Reactor Regulation, dated February ll,1980, the TMI-2 license has not been formally amended.
The requirements are reflected in the proposed Recovery Mode Technical Specifications presently pending before the Atomic Safety and Licensing Board.
Hereafter in this Amendment of Order, the requirements in question are identified by the applicable proposed Technical Specification.
II.
By letter dated March 5,1982, the licensee proposed changes to the super-visory authority under which TMI-2 Radiological Control Technicians (Rad.
Con Tech.) training currently falls.
The licensee has requested that Rad. Con. Tech training be removed from the cognizance of the Supervisor-Station Training, as presently required in TMI-2 Appendix A Technical Specification 6.4.1 and placed instead under the authority of the Vice-President for Radiological and Environmental Control.
Actual implementation of on-site training will be carried out under the direction of the Radiological Controls Department.
The staff has found this change to be acceptable.
The staff's safety assessment of this matter is set fortn in the concurrently issued Sa fety Evaluation.
This evaluation concluded, in material part, that the modi fication does not involve a significant hazards consideration and that there is reasonable assurance that the health and safety of the public l
l will not be endangered by operation in the modified manner.
Prior puolic t
l notice of;this Amendment of Order is therefore not required and the action is effectLe u an issuance.
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. It was further determined that the modification does not authorize a change in effluent types or total amounts nor an increase in power level and will not result in any significant environmental impact.
In light of this determination, it was concluded that the instant action is insignificant from the standpoint of environmental impact and, pursuant to 10 CFR j51.5 (d)(4), that an environ-mental impact statement or environmental impact appraisal and negative declaration need not be prepared herewith.
III.
Accordingly, pursuant to the Atomic Energy Act of 1954, as amended, the Director's Order of February 11, 1980, is hereby revised to incorporate the deletions, additions, and modifications. set forth in Attachment A hereto.
For further details with respect to this action, see (1) Letter to B. Snyder, USNRC, from R. Arnold, GPU Nuclear, Technical Specification Change Request No. 28 dated March 5, 1982 and (2) The Director's Order of February 11, 1980.
All of the above documents are avialable for inspection at the Commission's Public Document Room,1717 H Street, N.W., Washington, D.C., and at the Commission's Local Public Document Room at the State Library of Pennsylvania, Government Publications Section, Education Building, Commonwealth and Walnut Streets, Harrisburg, Pennsylvania 17126.
l FOR THE NUCLEAR REGULATORY COMMISSION krN/d b l
Harold R. Centon, Director Office of Nuclear Reactor Regulation Effective Date: June 16, 1982 Dated a t Bethesca, 'ta rylanc fL
SAFETY EVALUAT10N BY THE OFFZCE OF NUCLEAR REACTOR REGULAT10N GENERAL PUBLIC UTILITIES NUCLEAR CORPORATION DOCKET NO. 50-320 THREE MILE ISLAND NUCLEAR STATION, UNIT NO. 2 Introduction By letter dated March 5,1982 (4400-82-L-0030) the General Public Utilities Nuclear Corporation proposed changes to Technical Specification 6.4.1 of Appendix A to Operating License No. OPR 73 for the Three Mile Island Nuclear Station, Unit No. 2 (TMI-2).
The licensee requested changes to Appendix A of Operating License No. DPR-73 with regard to the supervisory authority under which the TMI-2 Radiological Controls Technicians (Rad. Con. Tech.)
training program currently falks.
Discussion and Evaluation In accordance with the TMI-2 Appendix A Technical Specification 6.4.1 Rad. Con.
Tech. training has been under the cognizance of the Supervisor - Station Training.
This Technical Specification Change Request proposes placing Rad. Con. Tech, training under the authority of the Vice President for Radiological and Environmental Control.
However, the responsibility for actual day-to-day, on-site implementa-tion of the training program will be delegated to the Director of the Radiological Controls Department.
In order to imorove tne qualifications of the TMI-2 Radiological Controls Tecnnicians, a Rad. Con. Tech. Training / Qualification program was established under the direction of the newly formed Unit 2 Radiological Control Training i
Department in November 1979.
This was in response to both company and NRC concerns and also to recommendations by an independent consultant in November 1979.
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. Section 6.4.1 of the TMI Technical Specifications has required a training and replacement 2:ning program under the direction of the Superviso r-S ta tion Training to meet or exceed the requirements and recommendations of Section 5.5 of ANSI N.18.1 1971 and Appendix "A" to 10 CFR 55.
Since it was not clear that Rad. Con. Tech. training was within the scope of the referenced ANSI standard, the discrepancy with the Technical Specification was not recognized.
Section 6.4.1 could not be met as long as Rad. Con. Tech, training was under the direction of the Supervisor-Station training.
This was brought to the Licensee's attention via Inspection Report 50-320/80-17 issued by the NRC on March 20, 1981.
This change request was submitted to correct this situation.
The proposed change of jurisdiction will also afford the Rad. Con. Tech training program the benefit of Supervisory and Management expertise in the radiological area, thereby further assuring an adequate training program.
In addition, this concept of having the training program under the direction of the Radiological Controls Department was endorsed by the Report of the Special Panel in December 1979 (NUREG 0640).
Environmental Consideration We have determined that the amendment does nut authorize a change in effluent types of total amounts nor an increase in power level and will not result in any significant environmental imcact.
Having mace tnis determination, we have further concluded that the amendment involves an action wnich is insignificant from the standpoint of environmental impact, and, pursuant to 10 CFR 51.5 (d)(2),
that an environmental impact statement or negative declaration and environmental impact aporaisal need not be orecared in connection with the issuance of this amencment.
Conclusion Based on the considerations discussed above, we have concluded that:
(1) Because the Amendment of Order does not involve a significant increase in the probability or consequences of accidents previously considered and does not involve a significant reduction in a margin of safety, it does not involve a significant hazards consideration.
(2) There is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner.
(3) Such activities will be conducted in compliance with the Commission's regulations and the issuance of this Amendment of Order will not be inimical to the common def6nse and security or to the health and safety of the public.
i Accordingly, the staff finds this Amendment of Order to be acceptable.
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FACILITY OPE?ATING LICENSE NO CPR-73 DOCKET NO. 50-320 Replace the following pages of the proposed Appendix "A" Tecanical Specifications with the enclosed pages as indicated.
The revised page contains vertical lines indicating the area of change, 6-4 I
6 son 2 wn
ADMINISTRATION CONTROLS 6.3 UNIT STAFF OUALIFICATIONS 6.3.1 Each member of the unit staff shall meet or exceed the minimum qualifica-tions of ANSI-N 18.1 of 1971 for comparable positions unless otherwise ncted in the Technical Specifications.
6.3.2 The Manager-Radiological Controls shall meet or exceed the cualifications of Regulatory Guide 1.8, September 1975.
Each Radiological Controls Technician in responsible positions / Foreman shall meet or exceed the qualifications of ANSI 18.1-1971, paragraph 4.5.2/4.3.2, or be formally qualified through an NRC approved TMI-2 Radiation Controls training program.
Individuals who do not meet ANSI 18.1-1971 Section 4.5.2 are not considered technicians for purposes of determining qualifications but are permitted to perform work for which qualifi-cation has been demonstrated.
All Radiological Controls Technicians will be qualified through training and examination in each area or specific task related to their radiological controls functions prior to their performance of those tasks.
6.4 TRAINING 6.4.1 A retraining and replacement training program for the unit staff shall be maintained under the direction of the Plant Training Manager - TMI-2 and shall meet or exceed the requirements and recommendations of Regulatory Guide 1.8 of 1977 and Appendix "A" of.10 CFR Part 55 except that Radiological Controls training may be under the direction of Vice President - Radiological and Environmental Controls.
6.4.2 A training program for the Fire Brigade shall be maintained under the direction of the Plant Training Manager - TMI-2 and shall meet or exceed the requirements of Section 27 of the NFPA Code - 1976.
6.5 REVIEW AND AUDIT 6.5.1 PLANT OPERATIONS REVIEW COMMITTEE (PORC)
FUNCTION 6.5.1.1 The Plant Operations Review Committee (PORC) shall function to advise the Director Site Operations on all matters related to nuclear safety and radioactive waste safety.
COMPOSITION
- 6. 5.1. 2 The Plant Operations Review Committee shall be composed of'the:
a.
Chairman -
wno shall have an academic degree in engineering or pnysical science field and a minimum of five years of applicable experience.
b.
1 Member -
wno snall meet or exceed the qualifications of Regulatory Guice 1.8, Septemoer 1975.
THREE MILE ISLAND - UNIT 2 6-3 PROPOSED
ADMIflISTRATIVE CONTROLS who shall meet or exceed the qualifications of c.
7 Members -
Section 4.4 of ANSI N18.1 - 1971.
The Director Site Operations shall designate the Chairman and the Vice Chairman from among the members of the Plant Operations Review Committee.
b THREE MILE ISLAND - UNIT 2 5-3a PROPOSED