ML20214G892
| ML20214G892 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 11/18/1986 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Kane W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| TAC-63540, NUDOCS 8611260215 | |
| Download: ML20214G892 (1) | |
Text
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b b C' Movember 18, 1986 Docket No. 50-289 MEMORANDUM FOR:
William F. Kane, Director Division of Reactor Projects, Region I FROM:
John F. Stolz, Director PWR Project Directorate #6 Division of PWR Licensing-B
SUBJECT:
REVIEW 0F TSCR 1El FOR TMI-1 Enclosed is an amendment request by GPUN for TMI-1 dated November 4, 1986.
The amendment was submitted to revise the Radiological and Environmental Controls Department organizational responsibilities and titles in the Administrative section of the TS.
Region I is requested.to review this amendment request and provide a safety evaluation suitable for use in an amendment and a SALP input. Work for this effort is to be charged to TAC 63540. The requested completion date is January 1, 1987. This date has been tentatively discussed with Randy Blough of your staff.
If you need additional information concerning this request, please contact the assigned Project Manager, Thierry Ross at 492-8324.
/S/
John F. Stolz, Director PWR Project Directorate #6 Division of PWR Licensing-B
Enclosure:
As stated cc w/ enclosure:
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Route 441 South Middle w, Pennsylvania 17057-0191 TELEX 84 2386 November 4,.1986 Writer's Direct Dial Numg~r:
5211-86-2161 Office of Nuclear Reactor Regulation Attn: John F. Stolz, Director PWR Projects Directorate No. 6 U. S. Nuclear Regulatory Commission Washington, DC 20555
Dear Mr. Stolz:
Three Mile Island Nuclear Station, Unit I, (THI-1)
Operating Licensa No. DPR-50 Docket No. 50-289 Technical Specification Change Request No.161 Enclosed are three originals and forty conformed copies of Technical Specification Change Request No.161.
Also enclosed is one signed copy of the Certificate of Service for this request to the chief executives of the township and county in which the facility is located, as well as the Bureau of Radiation Protection.
Pursuant to 10 CFR 50.91(a)(1), we enclose our analyses, using the standards in 10 CFR 50.92 of significant hazards considerations. As stated above, pursuant to 10 CFR 50.91(a) of the regulations, we have provided a copy of this letter, the proposed change in Technical Specifications, and our analyses of significant hazards considerations to Thomas Gerusky, the designated representative of the Commonwealth of Pennsylvania.
Pursuant to the provisions of 10 CFR 170.21, enclosed is a check for $150.00 as payment of the fee associated with Technical Specification Change Request No. 161.
Sincerely,
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kill Vice President & Director, THI-l HDH/DVH/spb
Enclosures:
- 1) Technical Specification Change Request No.161
- 2) Certificate of Service for Technical Specification Change Request No. ~61
- 3) Check No. 245896 CO cc:
J. Thoma
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I Conte R.PU Nuclear Corporation is a subsidiary of the General Public Utilities Corpc, ration G
(c.c') wfFje c r{f 6D 00
UNITED STATES OF AMERICA 8
NUCLEAR REGULATORY COMMISSION IN.THE MATTER OF DOCKET N0. 50-289 LICENSE N0. DPR-50 GPU NUCLEAR CORPORATION This is to certify that a copy of Technical Specification Change Request No.161 to Appendix A of the Operating License for Three Mile Island Nuclear Station Unit 1, has, on the date given below, been filed with executives of Londonderry Township, Dauphin County, Pennsylvania; Dauphin County, Pennsylvania; and the Pennsylvania Department of Environnental Resources, Bureau of Radiation Protection, by deposit in the United States mail, addressed as follows:
Mr. Jay H. Kopp, Chairman Mr. Frederick S. Rice, Chairman Board of Supervisors of Board of County Commissioncrs Londonderry Township of' Dauphin County R. D. #1, Geyers Church Road Dauphin County Courthouse Middletown, PA 17057' Harrisburg, PA 17120 Mr. Thomas Gerusky, Director PA. Dept. of Environmental Resources s
Bureau of Radiation Protection P.O. Box 2063 Harrisburg, PA 17120 GPU NUCLEAR CORPORATION BY:
Vice President & Director, TMI-l DATE:
Nnvember 4. -1986
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' Technical Specification Change Request-No.':161 The Licensee requests'the attached pages 6-3, Figure 6-1, and Figure 6-2 replace pages 6-3, Figure 6-1 and Figure 6-2 of the existing Technical
+
Specifications.
It should be noted that this TSCR is a follow-on to TSCR 151. As such 'this TSCR should be coordinated with TSCR 151.
Reason for Change Long range plans for the Radiological Controls Department will result in certain TMI-2 radiological controls functions being transferred to the TMI-l organization.
This change will allow for the gradual and controlled phased merger of the two organizations.
Figure 6-1 is revised to better delineate the major functional responsibilities under the Vice President Radiological and Environmental Control (R&EC).
Figure 6-2 is revised to depict R&EC functional. sections providing support to TMI-1. Previously only the Radiological Controls Department was shown.
The function of each identified section remains constant, but periodically the detailed section organization car change to better accommodate the section function. This change of F.igure 6-2 permits the section organization changes without requiring unnecessary submittals.
Safety Evaluation Justifying Change The sections to be transferred will be fully staffed, will not create a new area in Unit 1, and will require no additional manpower from the current TMI-l Radiological Controls staff. The transfer will result in more functional responsibility for the existing TMI-1 Radiological Controls management, but it will not impact on the overall performance of the Department.
Therefore, this change will not have an affection operation of the plant, will not affect the technical content of the Safety Analysis Report, and will not affect technical content of the Technical Specifications.
Significant Hazards Consideration This proposed change is similar to Example (i) of the " Amendments not Likely to In/olve Significant Hazards Consideration" from the Federal Register Vol. 48, No. 67 at 14870 on April 6,1983.
This change is an administrative change in the Radiological Controls Department at TMI-1.
As such this TSCR does not:
(1) affect plant design or operation, and therefore would not involve a significant increase in the probability or consequences of an accident previously evaluated;
. i (2) involve a modification to the existing plant equipment and therefore would not create the possibility of a new or different kind of accident from any accident previously evaluated; (3) ' involve changes which would affect the safety analysis of the plant and therefore would not involve a significant reduction in the margin of safety.
As noted in the Safety Evaluation, this change will not affect the existing workload of the THI-l Radiological Controls staff. Therefore, significant safety hazards are not associated with this change.
Implementation It is requested that the amendment authorizing this change become effective upon issuance.
Amendment Fee (10 CFR 170.21)
Pursuant to the provisions of 10 CFR 170.21, attached is a check for $150.00.
i 9
I l
g.
A Site Fire Brigade ## of at least 5 members shall be maintained onsite at all times. The Site Fire Brigade shall not include members of the minimum shif t crew necessary for safe shutdown of the unit and any personnel required for other essential functions during a fire emergency.
h.
The Shif t Technical Adviscr shall serve in an advisory capacity to the Shif t Supervisor on matters pertaining to the engineering aspects assuring safe operation of the unit.
6.3 UNIT STAFF QUALIFICATIONS 6.3.1 Each member of the unit staff shall meet or exceed the minimum qualifications of ANSI /ANS 3.1 of 1978 for comparable positions unless otherwise noted in the Technical Specifications. Licensed operators shall meet the supplemental requirements specified in Sections A and C of Enclosure 1 of the March 28, 1980 NRC letter to all licensees.
Individuals who do not meet ANSI /ANS 3.1 of 1978, Section 4.5, are not considered technicians or maintenance personnel for purposes of determining qualifications but are permitted to perform work for which qualification has been demonstrated.
6.3.2 The Radiolcgical Controls Department Head or Deputy shall meet or exceed the qualifications of Regulatory Guide 1.8 of 1977.
Each Radiological Controls Technician / Supervisor shall meet or exceed the qualifications of ANSI-N 18.1-1971, paragraph 4.5.2/4.3.2, or be formally qualified through an NRC approved TMI-l Radiation Controls training program. 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.
6.3.3 The Shif t Technical Advisors shall have a bachelor's degree or equivalent in a scientific or engineering discipline with specific training in unit design, response and analysis of transients and accidents, s.
6.4 TRAINING S.4.1 A retraining and replacement training program for the unit staff shall be maintained under the_ direction of the Manager, Plant Training - TMI mm and shall meet or exceed the requirements and recommendations 6f Regulatory Guide 1.8 of 1977 and Appendix "A" of 10 CFR Part 55 except
- g that Radiological Controls training may be under the direction of the
.o n Vice President - Radiological and Environmental Controls. Licensed 8
operators shall meet the supplemental requirement specified in Section jh A and C of Enclosure 1 of the March 28, 1980 NRC letter to all o
licensees.
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6.4.2 A training program for the Fire Brigade shall be maintained under the direction of the Manager, Nant Training - TMI and shall meet or excmd
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the requirements of Section 27 of the NFPA Code - 1976.
6.5 REVIEW AND AUDIT 6.5.1 TECHNICAL REVIEW AND CONTROL 6-3 Amendment Nos. JI, N, N, 77, N
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