ML20134K220

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Safety Evaluation Supporting Amend 77 to License DPR-6 Re Administrative Changes Related to Radiological Effluent Tech Specs
ML20134K220
Person / Time
Site: Big Rock Point File:Consumers Energy icon.png
Issue date: 08/26/1985
From:
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20132C980 List:
References
NUDOCS 8508300072
Download: ML20134K220 (4)
v • d • e


Text

UNITED STATES g g NUCLEAR REGULATORY COMMISSION O ( j WASHINGTON, D. C. 20555

  • s., ...../

SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING APEFTMEf:T fl0. 77 TO FACILITY OPERATING LICENSE NO. DPR-6 CONSUMERS POWER COMPANY BIG ROCK POINT PLANT DOCKET NO. 50-155 ADillflISTRATIVE TECHNICAL SPEC 9ICATION CHANGES RELATED TO PADIOLOGICAL EFFLUENT TECHNICAL SPECIFICATIONS (RETS)

1.0 INTRODUCTION

Consumers Power Company (CPC) (the licensee) submitted an application, dated Jeruary 7,1985 as revised March 14, 1985 for an amendment of the Technical Specifications, appended to License No. DPR-6 for the Big Rock Point Plant. The following provides an evaluation of the proposed changes not included in the preceding evaluation related to the RETS.

A Notice of Consideration of Issuance of Amendnent to License and Proposed No Significant Hazards Consideration Determination and Opportunity for Hearing related to the requested action was published in the Federal Register on June 4, 1985 (50 FR 23546). No public coments or requests for hearing were received.

2.0 DISCUSSION AND EVALUAT10N 2.1 Section 6.4.1(c) of the existing Technical Specifications references Section 6.4.3(c) for alarm setpoints of the Energency Condenser Vent Monitors. The proposed charge reformats Section 6.4.1(c) to include Section 6.4.3(c). This is purely an administrative change and therefore is found to be acceptable.

2.7 Sx tion 6.4.2(a) of the existing Technical Specifications describes the requirement for an Area Monitoring System. This system is composed of fixed gama monitors. The current specifications also provide the recuirements for the location of these monitors as well as their operating ranges, output indication locations, and alarm setpoints as referenced in Section 6.4.3(e). Section 6.4.3(e) is to be appended to currently existing Section 6.4.2(a)(iii), and provides the alarm setpoints and instructions for maintenance and repairs.

This change is a relocation of existing specifications, administrative in nature, and is therefore found to be acceptable.

2.3 Section 6.4.2(c) of the existing Technical Specifcations will be replaced by existing specifications 6.4.?(e) and 6.4.3(h). This proposed change is a relocation and reformatting of two existing specifications into one specification. This is er administrative 8509300072 B50026 DR ADOCK O g5

change necessary for the incorporation of the RETS related changes. The intent of the existing requirement of technical specification 6.4.2(c) shall be met using the high range. noble stack-cas effluent monitor.

This instrueentation is included as part of RETS. Since the intent of environnental release monitoring is met, the deletion of the existing technical specification 6.4.2(c) is found to be acceptable.

2.4 Section 6.4.2(d) of the existing Technical Specifications is being replaced with erf sting specification 6.4.3(f). An additional calibration requirement has been added to this specification adding conservatism to the calibration frequency. The existing specification 6.4.2(d) is proposed to be part of the rew specification 6.4.3, Reactor Water Level Monitors in the Reactor Depressurization System. Both of the above changes are administrative in nature and are found to be acceptable.

P.5 Section 6.4.3(g) of the existing Technical Specifications is being relocated and appended to Specification Section 6.4.3 (described above). This is purely an administrative change and is therefore found to the be acceptable.

2.6 The table in Section 7.6 of the existing Technical Specifications has been changed to accomodate the RETS related changes as well as the administrative changes. The administrative changes are addressed below,

a. Control Rod Performance - The performance frequency of this test has recently been changed from "at each major refueling shutdown,"

to "at each major refueling shutdown, but no less than once every 20 months". This change was not related to the RETS, but was a result of the issuance of Amendment No. 73 to the Big Rock Point Technical Specifications, dated May 1, 1985. Since the licensee's RETS application was submitted on January 7,1985, as revised March 14, 1985, this RETS related change, as submitted, is not applicable. Therefore, since the currently existing surveillance technical specification for Control Rod Performance testing is still velid and unchanged, it has been incorporated into this amendment as it currently exists,

b. Calibration of Emergency Condenser Vent Monitors - The " referenced nrocedure" within the current Technical specifications is depicted as Section 6.4.3. The specific Section applicable to these monitors, Section 6.4.3(c), has been relocated to Section 6.4.1, as discussed in P.1, above. This change is purely administrative and is therefore found to be acceptable,
c. Calibration of Area Monitoring System - As described in 2.3 above, the calibration frequency is now provided in Section 6.4.2 and will no longer be provided in Section 6.4.3 due to the RETS implementation.

This change is purely administrative and only involves the renumbering of a reference provided in the existing Technical Specifications, and is therefore found to be acceptable.

d. Channel Check of High Range Containment Gemma Monitors and Channel Calibration of Hioh Pange Containment Gamma Monitors - As described in 2.3 above, the Channel Check and Calibration for these monitors is new provided in Section 6.4.2 and will no longer be provided in Section 6.4.2 due to the RETS implementation. This change is purely administrative and only involves the renumbering of references provided in the existing Technical Specifications, and is therefore found to be acceptable.

P.7 Table 13-1 Item 5d., Hi Range Noble Gas Monitor, (PRNGM), of proposed Specification Section 13.1.1.1, was added to the facility Technical Specifications via Amendment No. 75, dated June 10, 1985. The HRNGM is an integral part of the stack-gas monitoring system. This instrumentation was included in Table 13-1 because Section 6.4.3 has been changed to accommodate the RETS implementation. Therefore, Section 6.4.3 will no longer be applicable for this instrumentation.

This HRNGM remains a requirement and the surveillances are no less conservative. The Action for an Inoperable channel has remained unchanged except for the requirement of the submission of the Special Report.

Current Technical Specifications require submission with 14 days after the identification of the failure. The proposed change will permit submission with 30 days following the event. This chenge in reporting time provides the licensee with additional time to identify the root cause of the failure, and the schedule for restoring the system to Operable status. Table 13-2 provides the Surveillance Requirement for Channel Check, Source Check, Channel Calibration, and Channel Functional Test. The frequency of the Ch6nnel Calibration will be changed from once each refueling outage to once every 18 months.

This Surveillance change adjusts the celibration frequency to align with all of the other RETS-related instrumentation channel calibrations.

The above changes are primarily administrative and also provide clarification of existing specifications. Therefore, the staff finds these changes to be acceptable.

P.8 Table 13-2, Notation of proposed Technical Specification 13.1.1.2, Mete (5), is to be part of the Channel Calibration requirement for the HPNOM as well as Air Ejector Off Gas. This note provides for ALARA considerations and will minimize personnel exposure during calibrations, and is therefore found to be acceptable.

3.0 EllVIRONMENTAL CONSIDERATION This amendment involves changes to requirements with respect to the installation or use of facility compenents located within the restricted area as defined in 10 CFR Part 20 and chances to the surveillance requirements. The staff has determined that the amendment involves no significant increase in the amounts', and no significant change in the types, of any effluents that may be released offsite and that there is no significant increase in individual or cumuletive occupational radiation exposure. The Commission has previcusly issued a proposed finding that this amendment involves no significant hazards consideration and there has been

ne public coment on such finding. Accordingly, this amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.??lc)(9).

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

4.0 CONCLUSION

We have concluded, based on the considerations discussed above, that:

(1) there is reasonable assurance that the health and safety of the public will not be erfargered 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 ACKNOWLEDGEMFNT This Safety Evaluation has been prepared by Thoras S. Potella.

Dated: August 26, 1985

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