ML20112G237

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Safety Evaluation Supporting Amends 86 & 79 to Licenses DPR-19 & DPR-25,respectively
ML20112G237
Person / Time
Site: Dresden  
Issue date: 03/20/1985
From:
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20112G219 List:
References
NUDOCS 8503280126
Download: ML20112G237 (4)


Text

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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENDMENT NO. 86 TO PROVISIONAL OPERATING LICENSE NO. DPR-19 AND AMENDMENT NO. 79 TO FACILITY OPERATING LICENSE NO. DPR-25 COMMONWEALTH EDISON COMPANY DRESDEN NUCLEAR POWER STATION, UNIT NOS. 2 AND 3 DOCKET NOS. 50-237/249

1.0 INTRODUCTION

On February 17, 1983, Commonwealth Edison Company (CECO) submitted a proposed amendment request for changes to the Technical Specifications (TS) relating to administrative controls. Before this request had been acted upon by the staff, the Nuclear Regulatory Commission, on August 29, 1983 (48 FR 39046) and July 26, 1983 (48 FR 33858), amended its regulations, 10 CFR 50.72 and 50.73, to revise imediate reporting requirements and to establish a new reporting system for significant events at nuclear power piants. On December 19, 1983, the Division of Licensing issued Generic Letter (GL) 83-43, " Reporting Requirements of 10 CFR Part 50 Sections 50.72 and 50.73, and Standard Technical Specifications" infoming all licensees of the revision to Section 50.72, Immediate Notification Require-ments, and the addition of a new Section 50.73, Licensee Event Reporting System. The licensees were requested to update their TS to include the new requirements and model Standard Technical Specifications were provided showing the revisions that should be made in the " Administrative Control" and " Definition" sections. The letter also requested the licensees to review and update cther areas of the TS concerning reportability, as required.

i CECO responded to GL 83-43 with a submittal dated April 27, 1984 which l

was responsive to the new regulations and updated the February 17, 1983 submittal to reflect staff concerns.

Following this, the entire TS for both units were compu.terized and reissued on August 6, 1984 in a format which had improved legibility and versatility.

By letter dated October 24, 1984, Commonwealth Edison Company (CECO) submitted proposed amendment changes confoming to the new format.

l The proposed amendments contained several miscellaneous changes to the l

facilities' TS. The proposed changes included:

(1) changes to reporting requirements to reflect the requirements of 10 CFR 50.73, (2) changes l

to position titles and organization chan Operator requirements of 10 CFR 50.54(m)ges, (3) additional Senior (2)(i) and (ii), (4) changes to reflect the current NRC organization and (5) corrections of miscellaneous descriptions, grammatical and typographical errors. These changes are primarily administrative in nature and do not adversely affect the safety of the plant nor the general public.

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This Safety Evaluation documents the basis for acc'eptance of requested changes submitted in the October 24, 1984 letter and their impact on the operation and administration of plant activities.

A Notice of Consideration of Issuance of Amendments to License and Proposed No Significant Hazards Consideration Detemination and Opportunity for Hearina related to the requested action was published in the Federal Reaister on December 31, 1984 (49 FR 50800). No public comments or requests for hearing were received.

2.0 EVALUATION 2.1 Changes to Reporting Requirements Sections 3.12.A.2.b; 3.12.B.2; 3.12.B.3; 3.12.D.5; 3.12.E.3; and 3.12.F.4 are revised to require that reports be submitted per 10 CFR 50.73. Report content is revised to include a description of actions taken associated with inoperable equipment.

Sections 6.1.G.I.a.7; 6.1.G.2.a.10; 6.3; 6.4; and 6.5.A.3 are revised to change occurrence to event in accordance with terminology used in 10 CFR 50.73 and follow the guidance given in Generic Letter 83-43.

These changes bring the facilities' TS into confomance with 10 CFR 50.73 and are therefore acceptable.

2.2 Changes to CECO Position Titles and Organization Sections 6.1.B; 6.1.C; 6.1.D; 6.1.G.1; 6.1.G.I.a; 6.1.G.1.a.10; 6.1.G.b.12; 6.1.G.2.a; 6.1.G.2.a.5; 6.1.G.2.a.8; 6.1.G.2.a.9; 6.1.G.2.b; 6.1.G.2.c; 6.1.G.2.d.1; 6.2. A.14; 6.2.C.1; 6.2.C.2 6.3; and 6.4 are changed to reflect position titles and organization changes made in revised Figure 6.1-1.

Figure 6.1-1, " Corporate Organization," present page 6-3, and Figure 6.1-2, " Station Organization," present page 6-4, have been consolidated into one figure, 6.1-1 " Corporate and Station Organization." These changes reflect the current CECO organization as depicted in Ceco Quality Assurance Manual, Revision 91; the most significant change being that the Manager Quality Assurance now reports to the Chairman instead of the Vice Chairman of Ceco, giving further independence to the Quality Assurance Organization. Revision of these figures updates the Dresden TS to depict the organization chart currently in use for other CECO facilities and their associated documents. This organization continues to satisfy the requirements of 10 CFR Part 50, Appendix B, Criterion 1.

As these changes are solely administrative, the staff has determined they are acceptable.

o

. 2.3 Minimum Shift Manning Requirements Table 6.1.1, " Minimum Shift Manning Chart," has been revised to conform with the requirements of 10 CFR 50.54(m)(2)(1) and (ii). Although Dresden I has been unofficially retired by the licensee (press release dated August 31,1984), the Unit 1 operating license is still in effect. This unit is completely defueled and will remain so.

It is therefore pennanently in cold shutdown. The TS have been revised to increase the number of Senior Operators from one to two when two of the three units are in cold shutdown and the third (either Unit 2 or Unit 3) is above cold shutdown. This change is acceptable.

2.4 NRC Organization Sections 6.6; 6.6.A.3; and 6.6.C.2.a.1.a are amended to reflect that the current NRC organization designations on the TS, Director of the appropriate Regional Office, and, Office of Management Information and Program Control, are revised to, Regional Administrator of the appropriate Regional Office, and, Office of Resource Management, respectively. These changes correct present errors and reflect the current titles and, therefore, are acceptable.

2.5 Miscellaneous Descriptions, Grammatical and Typographical Corrections Section 6.1.A is revised to include the publication date of ANSI N18.1. to which Ceco is committed. Section 6.1.G.1.b.5 is revised to require audits of the Facility Emergency Plan at least once per 12 months.

Section 6.1.G.I.b.6 is revised to require audits of the Facility Security Plan and implementing procedures at least once per 12 months.

Section 6.2.E is revised to require that drills of the emergency procedures for emergency conditions involving potential or actual release of radioactivity, etc., shall be conducted at the frequency specified in the Generating Station Emergency Plan.

Section 6.7.A has been revised to correct the license number (Unit 2 only).

Section 6.9.C.2 and 6.10.A.1 have been revised to capitalize the words, "Onsite Review Function."

The above changes were made to clarify the TS or are administrative in nature; therefore, the staff finds them to be acceptable.

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3.0 ENVIRONMENTAL CONSIDERATION

This amendment relates to changes in recordkeeping, reporting, or administrative procedures or requirements. Accordingly, this amendnent meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(10).

Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of this amendment.

4.0 CONCLUSION

S The staff has concluded, based on the considerations discussed above, that:

(1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, and (2) such activities will be conducted in compliance with the Commission's regulations and the issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public.

5.0 ACKNOWLEDGEMENT The following staff members have contributed to this evaluation:

P. Eng and R. Gilbert.

Dated: March 20, 1985 O

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