ML20033C478
| ML20033C478 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 11/25/1981 |
| From: | Hukill H METROPOLITAN EDISON CO. |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20033C475 | List: |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737 NUDOCS 8112030298 | |
| Download: ML20033C478 (6) | |
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METROPOLITAN EDIS0N COMPANY JERSEY CENTRAL' POWER & LIGHT COMPAhT AND.
PENNSYLVANIA ELECTRIC COMPAhT THREE MILE ISLAND NUCLEAR STATION, UNIT 1 Operating License No. DPR-50 Docket No. 50-289 Technical Specification Change ker,oest No. 100B This Technical Specification Change Request is submitted in support of Licensee's request to change Appendix A/B to Operating License No.
DPR-50 for Three Mile Island Nuclear Station, Unit 1.
As e parc of this request, proposed replacement pages for Appendix A/B are also included.
METROPOLITAN EDISON COMPAhT By Di ector, TMI-1 Sworn and subscribed to me this c7 6 day of $$0@)yd4A.,, 1981.
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Notary y c
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I FAFRA JOY LUBRECHT4 otary Public Mddietown, Dauphin County, Ps
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UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION IN THE MATTER OF DOCKET NO. 50-289 LICENSE NO. DPR-50 METROPOLI %N EDISON COMPANY This is to certify that a copy of Technical Specification Change Request No.100Bto Appendix A/B of the Operating License for Three Mile Island Nuclear Statica Unit 1, has, on the date given below, been filed with the U.
S. Nuclear Regulatory Commission and been served on the chief executives of Londonderry Township, Dauphin County, Pennsylvania and Dauphin County, Pennsylvania by deposit in the United States mail, addressed as follcws:
Mr. Donald Hoover, Chairman Mr. John E. Minnich, Chairman Board of Supervisers of Board of Cc.c.nty Commissioners Londonderry Township of Dauphin County R.D. #1, Geyers Church Road Dauphin County Courthouse Middletown, PA 17057 Harrisburg, PA 17120 METROPOLITAN EDISON COMPANY By Dirictor, TMI-1 Dated:
Novcmber 25, 1981
1.
TECHNICAL SPECIFICATION CHANGE REQUEST NO. 1006 The Licensee requests that the attached revised pages replace the following pages of the existing Technical Specifications.
A. Appendix A Replace page iv Replace page vli Replace page 6-1 thru 6-27 Replace Figure 6-1 (pages 1-4)
B. Apoendix B Replace pages i and il Replace pages 1 thru 24 REASON FOR THE CHANGE REQUEST The attached changed pages are a result of meetings between represen-tatives of tne Licensee and NRC on August 2, 1981 and September 3, 1981 concerning TSCR 100 dated April 10, 1981 (L1L 093) and TSCR 100A cated August 13, 1981 (L1L 209). Change bars indicate changes from the existing Technical Specifications (including Amendment 72) and are summarized below:
Section 6.1 Resoonsibility
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Has been revised to reflect current wording used in the standarized Technical Specification and reflects the GDU Nuclear Corporation Title. Tne Vice President TMl-1 has become the position responsible under the Technical $pecifications. Additionally, th' comroand and control function of the Shift Supervisor is delineated.
Section 6.2 Organization lies been revised to chow the GDU Nuclear corporation which was the subject of TSCR No. 98.
the single organization chart has become two and no reflects the corporate anc unit staff respectively. Addi-tional l y, the minimuni shi f t crew composition has been updated to ref lect the ASLB DID and includes more standardized wording and j
the requirements for a Shift Technical Advisor (STA) (NUREG 0737).
l Section 6.3 Qualifications The unit staff as designated in Figure 6-2 has been upgraded to meet ANSI N 18.1-1978 except as otherwise noted in the Tech. Specs.
Additionally, requirements of the NRC letter of 3/28/80 have been added.
Specific qualification and training requirements for the TMI-l l
Radiolocica! Controls personnel and Shift Technical Acvisors are cis-Cussed.
Section 6.4 Training Additional sords have been added to indicate that training personnel
muau:l Trnining Program jney recoIva "dircction" in c:rtain phnsas of the -
program (such as course /examinaton content, qualification of Rad Con ca ste personnel or technically knowledgeable instructors) from the Vice gg President - Radiological Controls.
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_ Section 6.5 Review and Audit
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Has been revised to provide for interdisciplinary reviews and independent -
safety reviews using qualified individuals / groups rather than committees.
These qualified individuals /goups perform reviews of all activities now identified in Section 6.5.1 and 6.5.2.
The revised review process of section 6.5.1.14 vill be responsible for the review of activities of this section. This Responsible Technical Reviewer may obtain additional review support as he deems necessary to assure the quality of the review. His signature signifies in the same fashion as the previous PORC approval that -
the technical and safety considerations have been properly accounted for.
This releases the product for independent safety review and implementing approval.
Independent safety reviews of Section 6.5.2 have been similarly revised. The specific assignments of review areas will be controlled through the use of the GPUN Review and Approval Matrix.
Results of the reviews are made directly available to the TMI-1 Management organization.
Use of the GPU Nuclanr divisions inthis canner accomplishes the intent of Section 4.3 and 4.4 of ANSI N.16.7 (1976) and will eliminate the need for the currently established Plant Operations Review Committee (PORC) and Met-Ed corporate supporf staff.
The replacement of the FORC will enable plant staff supervisory personnel to devote their time to their primary duties without the time-consuming need f or participation in PORC meetings, which, under tne present organization requires much of the supervisors' time.
The proposed independent Onsite Safety Review Group (ISORG) will satisfy the requirements for an independent, full-time, safety engineering staff to be located onsite. The ISOR3 will be a group of technical personnel who are assigned onsite at TMi, but who report to the corporate level Nucleer Assurance Division. The ISORG will conduct an ongoing program to evaluate the technical adequacy and clarity of procecures important to safe operation of the plant (not necessarily a pre-implementation evaluation). Tne ISORG will evaluate TMI-1 operations from a safety perspective.
Audits of unit activities are performed by the Quality Assurance Department in accordance witn the Operational Quality Assurance Plan except for those in tne area of fire protection.
The General Office Review board has been deleted from the Tech.
Specs. since none of their functions are required by the Tech.
Specs.
Section 6.6 Reoortable Occurrences Has not been revised other than title changes.
Section 6.7 Safety Limit Violations has not been revised other than title changes.
G Section 6.8 Procedures Has been revised to include the requirements of the RETS and various station plans. Additionally, a section has been added concerning temporary changes not involving operational ac+ivities.
Section 6.9 Reoorting Reauirements Has been revised to include the requirements of the RETS and the unique reporting requirme'.ts of NUREG 0737.
Section 6.10 Record Retention Has been revised to reflect current wording used in Standardized Technical Specifications.
Section 6.11 Radiation Protec1 ion Program No change.
Section 6.12 High Radiation Area Has been revised to reflect lessons learned from the accident at TMI-2.
Section 6.13 Process Control Program (PCP)
Has been revised to include the requirements of the RETS.
Section 6.14 Offsite Dose CalculeT;on Manual (ODCM)
Has been revised to include the requirements of the RETS.
Section 6.15 Environmental Qualification Program No ;hange.
Section 6.16 lodine Monitoring Program Has been added to reflect the requirements of NUREG 0737.
Section 6.17 Major Changes te Racwaste Treatment Systems Has been revised to include the recuirements of tne RETS.
Ill.
SAFETY EVALUATION JUSTIFYING CHANGE This change describes the administrative structure and control of the GDU Nuclear Corporation as required by Tecnnical Specificatiors. This change enhances the independent revien process and incorporates recom-mendation of various committees and groups as a result of the accident at TMi-2.
Furthermore, it has been deternined that:
1.
The probability of occurrence or tne consequences of an accident I
4, ormalfundtionofequipmentimportanttosateTypreviously evaluated in the safety analysis report is not increased.
2.
The possibility of an accident or malfunction of a differelt type than any evluated previously in the saf ety analysis report is not increased.
3.
'he margin of saf ety def ino. in the basis of any Technical Specification is not reduced.
IV.
AMENDMENT CLASSIFICATION (10CFR 170.22)
This change, although administrative in nature, requests changes in the administrative controls associated with safety reviews and is therefore considered a Class ill License Amendment. A check for $4,000 was mailed with the original TSCR 100.
V.
,1 NPL ~ MENT AT I C:,
in order to finalize the necessary procedures and train personnel an implementation period of 4 months from the date of receipt of the applicable amencment is requested.