ML20245K522
| ML20245K522 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 06/26/1989 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20245K520 | List: |
| References | |
| NUDOCS 8907050153 | |
| Download: ML20245K522 (5) | |
Text
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Ik UNITED RTATES g
p, NUCLEAR REbuLATORY COMMISSION 7.
j WASHINGTON, D. C. 20555 k.....,/
jAFETYEVALUATION.BY.THE.0FFICE.0F. NUCLEAR.REACTORREGULATION
.RELATED.TO. AMENDMENT NO.
PERRY. NUCLEAR. POWER. PLANT,. UNIT.NO. 1 1
EKET.NO.50-440
1.0 INTRODUCTION
as amended July 21, 1988, the Clevelano By letter dated April 8, 1988,(CEI), et al., the licensees, submitted a Electric Illuminating Company proposed amendment to Facility Operating License No. NPF-58 for Perry Nuclear Power Plant, Unit 1.
The proposed amendment included a reorgani-zation of the Plant Operations Review Coirmiittee (PORC), Section 6.5.1 and numerous other administrative changes to the Technical Specifications (TS).
Partial response to the licensees' April 8, 1988 application was contained in Amendment No.13 to Facility Operating License NPF-58 for the Perry.
Nucle 6r Power Plant, Unit 1, issued on June 30, 1980. This amendment addresses the remaining items from the April 8, 1988 applic6 tion as amended on July 21, 1983.
A Notice of Consideration of Issuance of Amendment to Facility Operating
' License and Proposeo No Significant Hazards Consicaration Determination and Opportunity For Hearing related to the requested action was published in the Federal _ Register on May 31,1988 (53 FR 19832) and egain on March 22, 1989 (54 FR 11Ba5). No requests for hearing and no public comments were received.
2.0 DISCUSSION AND. EVALUATION The following are descriptions and evaluations of each of the proposed changes to TS for Perry Nuclear Power Plant, Unit 1.
None of these changes-involved physical modifications to the facility.
Description.of Change. Technical Specifications.Pages.1-7-and.6 15 The proposed change would revise the definition of a REPORTABLE EVENT by j
deleting the reference to 10 CFR 50.72 immediate notification requirements.
Evaluation The modified definition would be consistent with the recommendations of Generic Letter 83-43, dated December 19, 1983 which specified only conditions a
8907050153 890626 PDR ADOCK 05000440 P
'. 4 identified in 10 CFR 50.73 shall be defined as a reportable event. Since the events described in 10 CFR 50.72 are included in 10 CFR 50.73, the staff has I
determined that the proposed change is acceptable.
l Description.of Change.. Technical Specification Page 3/4.6 5 The proposed change would delete the footnote accompanying surveillance requirement 4.6.1.2.f which extended the leak testing of the main steam line isolation valves.
Evaluation This change is administrative in nature. The footnote was added by Amendment 5 to the Facility Operating License to extend the leak testing of main steam line isolation valves IB21-F022A and 1821-F028A until July 12, 1987. The footnote has expired and is no longer applicable; therefore the staff has determined that the change is acceptable.
Description of Change.. Technical Specification 3.7.3 The proposed change would delete the footnote referenced in TS 3.7.3 which suspended the operabilit uirement for autometic initiation of the reactor core isolation cooling (y req) system for the period April RCIC 10, 1987 through May 31, 1987.
Evaluation The original request to suspend the RCIC operability requirements was granted through Amendments 1 and 4 of the Facility Operating License. The suspension expired on May 31, 1987 and is no longer applicable. The deletion of the footnote is acceptable to the staff.
Description of Change,. Technical Specification..Section.4.7.7.1 The proposed change would correct the word " system" to " subsystem" in TS 4.7.7.1.b.1.
Evaluation The word replacement corrects a typographical error and is administrative in nature. The staff has determined that the change is acceptable.
Description.of. Change, Technical. Specification 4.8.1.1.2 The proposed change corrects the values corresponding to the electrical loads of one residual heat removal (RHR) and one high pressure core spray (HPCS) pump on their associated emergency diesel generators. The values would be changed from 725kw to 729kw and from 2200kw to 2400kw, respectively.
f Evaluation The proposed load values reflect actual loads listed in Table 8.2-1 in the Updated Safety Analysis Report. These correct previous load data associated with the RHR and HPCS pumps. The proposed changes are also conservative in nature. The staff has determined that the changes are acceptable.
Description of Change, Technical Specification Section 6 The following changes are proposed:
Section 6.3.1 would be changed to delete the exception to ANSI N18.1-1971 qualification requirements for the Senior Operations Coordinator.
The title, Manager, Nuclear Engineering Department would be changed to Director, Nuclear Engineering Department in Sections 6.2.3 and 6.5.3.
The Manager, Perry Plant Operations Cepartment (PP00) position would be renamed General Manager, PPOD in Sections 6.1, 6.2, and 6.5, The titles for all General Supervisors and General Supervising Engineers would be changed to Managers in Sections 6.4 and 6.5.
In Sections 6.5.1.1, 6.5.1.6, 6.5.2.7, 6.5.3.1, and 6.8.2, the reference to Managers, Perry Plant Departments would be revised to General Manager, PPOD and Director, PPTD for clarification.
The requirements for approval of temporary procedure changes would be moved frem Section 6.5.3.1.a to a new section 6.8.3.
The old Section 6.8.3 was renumbered as 6.8.4.
In Section 6.8.4.a, the "CS" would be deleted and " hydrogen analyzer portion of Combustible Gas Control" would be added to clarify the portion of the CS system included in the Primary Coolant Sources Outside Containment Program.
Due to a recent plant reorganization, the Site Protection Section now reports to the newly-created Nuclear Support Department (NSD) via the Director, Perry Plant Technical Department. Specification 6.5.3.1.f has been revised to ir.dicate that Security Plan changes and Security Plan implementing instructions will now be approved by the Director, Nuclear Support Department, or Director, Perry Plant Technical Department, as appropriate.
Evaluation All of these changes are administrative in nature. On Page 6-7. Specification 6.3.1 is being revised to delete the exception to ANSI N18.1-1971 qualification requirements for the Senior Operations Coordinator since these qualifications
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t l
-4 are now being met. Personnel title changes are being made to be consistent with the current plant organization titles. Moving the requirements for approval of temporary procedure changes from Section 6.5.3.1.a to 6.8.3 does not change the review process or the approval requirements. These proposed 1
changes are considered acceptable by the staff.
Description of Change, Technical Specification Section 6.5.1 i
The proposed changes modify the composition and responsibility of the Plant Operations Review Comittee (PORC). The General Manager, PPOD and the Technical Supervisor, PPTD have been removed from serving on the comittee.
The Director, PPTD and the Manager, Operations Section have been assigned as I
the Chairman and Vice Chairman, respectively. The Principal Nuclear Operations j
Engineer and General Supervising Engineer, Outage Planning Section, have been removed which eliminates an additional two positions in PORC. The definition of Quorum in 6.5.1.5 has been changed to require the Cnairman or the designated alternate and at least four members present to correspond to the reduced size i
of the committee. The total committee size is reduced from 13 members to 9.
I Section 6.5.1.3 was revised to reduce the number of allowable participating alternates from three to two.
Section 6.5.1.6 h, i and n would be revised to delete the requirement to submit to the Nuclear Safety Review Committee a report recommended changes of the Security Plan, Emergency Plan, and Fire Protection Program.
Evaluation The original PORC board consisted of the General Manager, PPOD as chairman, three vice chairman and nine regular members. A quorum was defined as the i
chairman and six members which included no more than three alternates. The proposed reorganization will reassign the Director, PPTD and the Manager, Operations Section to the positions of chairman and vice chairman respec-tively. The removal of the Manager, PPOD, Technical Superintendent, PPTD, Principal Nuclear Operations Engineer and General Supervisor, Engineer Outage Planning Section will reduce the board to nine permanent members. A quorum will require the presence of the chairman and at least four members with no more than two alternates. The ratio of permanent members to alternates is essentially unchanged, in that the majority of personnel attending a PORC meeting will always be permanent members.
The changes in Section 6.5.1.6 are administrative in nature. Deleting these reporting requirements will make this section consistent with the responsibili-ties of the Nuclear Safety Review Committee specified in TS 6.5.2.7.
The review and approval of the PORC recommendations of the Security Plan, Emergency Plan and Fire Protection Program are the responsibilities of the General Manager, PP0D and/or Directors, PPTD or NSD as required by TS 6.5.3.1.
', The reorganization of the PORC will not interfere with its intended function.
The PORC members advise the General Manager, PP0D on matters related to nuclear safety. This individual is being renoved from the PORC since it is felt that the role of the PORC could be better performed if this position were independ-ent of the PORC. The Principal Nuclear Operations Engineer is being removed from the PORC since he is also functioning as the Nuclear Safety Review Comittee Chairman. The General Supervising Engineer, Outage Planning Section, is being romoved because the position is not required. The Technical Super-intendent, PPTD, is being removed since the Director, PPTD, will now serve as chairman. The remaining PORC members have an adequate knowledge of the various aspects of nuclear power plan operations. The ANSI N18.7-1976 endorsed by Regulatory Guide 1.33 and Chapter 13.4 of the Standard Review Plan describe the general characteristics and responsibilities of the operations review committee.
The proposed changes do not conflict with these standards, and are therefore considered acceptable by the staff.
3.0 ENVIRONMENTAL CONSIDERATION
This amendment relates to changes in surveillance requirements and changes in recordkeeping, reporting or administrative procedures or requirements.
The staff has determined that the amendments involve no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that these amendments involve no significant hazards consideration and there has been no public comment on such finding. Accordingly, the amendment meets the eligibility criteria for categoricalexclusionssetforthin10CFR51.22(c)(9)and(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
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 Comission'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.
Principal Contributor:
A. M. Bongiovanni Dated: June 26, 1989