ML20137Y643
| ML20137Y643 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 11/22/1985 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20137Y628 | List: |
| References | |
| TAC-53503, NUDOCS 8512110093 | |
| Download: ML20137Y643 (5) | |
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UNITED STATES
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NUCLEAR REGULATORY COfellSSION a
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SAFETY EVALUATION REPORT RELATED TO AMEN 0 MENT N0. 49 TO FACILITY OpfRATING LICENSE kPF-g l
AND TO AMENOMENT N0. 30 TO FACILITY GPERATING LICENSE NPF-17
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DUKE POWER COMPANY j
MCGUIRE NUCLEAR STATION. UNITS 1 AND 2 INTRODUCTION
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By letter dated January 12, 1984, DukePowerCompany(thelicensee)' pro-l posed an amen hent to License No. NPF-9 which would change the completion date in License Condition 2.C.(11)f.(3) for upgrading the Core Exit Thermo-couple (CET) System. By letter dated January 17, 1985, the licensee proposed amenhents to License No NpF-9 and NPF-17 which would change Surveillance Specifications 4.11.1.3.1 and 4.11.2.4 with respect to dose l
projections for normal plant releases. The NRC staff has evaluated these proposed amendments.
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EVALUATION l
L 1.
Schedule Change for Unorading the Unit 1 Core Exit Thermocouple 5.vstem Outsfee containment Upgrading of the McGuire CET system to the criteria in NUREG-0737,
" Clarification of TMI Action Plan Requirements " Item !!.F.2 I
" Inadequate Core Cooling Instruments," is being accomplished in two I
phases. The first phase was completed during the first refueling of t
l each McGuire Unit and involved upgrading the in containment portion '
l of the system. This included meeting _ qualification and separation i
requirements. The second phase will involve upgrading of the control room displays and is being accomplished to a schedule providing for l
integration with the licensee's Control Room Design Review and Regula-l tory Guide 1.g7 Accident Monitoring Instrumentation Review perfomed in accordance with Supplement I to NUREG-0737, " Requirements for Emergency Response Capability." Such integration is desirable in that it provides for the proper considerat'on of all wrtinent criteria in the final design of the display system.
towever, the l
1 schedule for completion of the upgrade required by Unit 1 License Condition 2.C.(11)f.(3) does not provide for this integration.
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l On June 15, 1984 the Commission issued an Order Confiming Licensee Commitments on Emergency Response Capability. The Order identified l
and required implementation of licensee's schedular commitments for l
I providing submittals and for implementing certain actions from Supple-l ment 1 to NUREG-0737. Item 3a of the table within the Order addressed i
0512110093 H51122 j',DH ADOCKOS00g9
, a requirement that licensees submit a re p rt for implementation of the provisions of Regulatory Guide 1.97, Revision 2, and noted that this requirement had been completed for the McGuire Nuclear Station. Prior to issuance of the Order, and by letter dated March 29, 1984, thd licensee had provided a response to Item 3a which stated, in relevant part (page 5-20), that "The qualified in containment portion of the core exit thermocouple system will be installed prior to startup following the first refueling outage for each unit. The Class 1E backup display (the remaining ex-containment portion) will be added by the end of the first refueling outage following January 1986 for each unit, contingent upon equipment availability."
License Condition 2.C.(11)f.(3) of the operating Ifcense for McGuire Unit 1 as last amended December 31,1981 (prior to the Order). required the licensee to upgrade the outside containment portion of the CET system no later than December 31, 1983. On December 30, 1983, the licensee provided initial notification to the NRC of its inability to comply with this License Condition. By letter dated January 12, 1984, the licensee requested that the Unit 1 license condition be changed with respect to the outside containment portion of the CET system to delete the specified implementation date and substitute a requirement that the licensee " provide a schedule for upgrade of the remainder of the system in the Regulatory Guide 1.97 Accident Monitoring Revie'w Report submitted pursuant to NUREG-0737, Supplement 1."
By letter dated September 17, 1984, the NRC infomed the licensee that "(3) the proposed schedules to upgrade the CET system...by the first refueling outage of each unit after January 1986.... are acceptable."
The Class 1E backup display w111 provide a temperature range from 200'F to 2300'F which does not rely on the plant computer, and its channels will be powered by a battery-backed power supply. Once installed, it will provide improvement in the reliability and human factors aspects of existing displays. However, the Connission finds that the extension of the implementation date for this upgrading of the outside contain-ment portion of the CET system beyond December 31, 1983, does not involve significant adverse safety considerations because the themo-couple mon' toring system as presently installed is a simple but reasonably reliable and accessible system. The system presently has the following capabilities:
(a) A spetta11y oriented core map is available on demand which,
indicates the temperature at core exit thermocouple locations.
This map can be displayed or printed on demand.
(b) An example of the McGuire selective readings is an on-demand tabular listing of instantaneous incore themocouple values.
This Itsting can be displayed or printed on demand.
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3 (c) Direct readout of average and instantaneous values, as well as hard-copy capabilities, is provided for thermocouple tempera-tures. The range is 0-2300'F.
(d) Trend capability showing temperature-time histories is designed into the system. Strip chart recorder points are available to assign to any incore thermocouples on demand. In addition,'a point-value trend printout is available on the control room typer.
(e) Alarm capability is provided in conjunction with the Subcooling Monitor, which uses the average of valid thermocouple readings in its calculations and alarms when the value drops below the setpoint.
(f) The cathode ray tube displays are designed for rapid operator access and ease of viewing data. In addition, the incore program has a validity-check comparison w'iich reduces the probability of accessing false readings.
Accordingly, the Consiission finds that the proposed change to Unit 1 License Condition 2.C.(11)f.(3) provides for consistency between the Operating License and the Conmiission's Order of June 15, 1984, and letter of September 17, 1984, and that the existing capabilities of the installed CET system are such that deferring the implementation date for upgrading the outside containment portion of the system beyond December 31,1983, does not create a significant adverse impact upon safety and, therefore, is acceptable.
2.
Clarification of Dose Projections for Nmal Releases By letter dated January 17,1985, the licensee proposed changes to eliminate ambiguities in two surveillance requirements in the McGuire Unit 1 and Unit 2 Technical Specifications for Radweste Treatment' Systems by more clearly indicating that the requirements for dose pro-tections are intended only with respect to untreated releases. Spect-fically, Surveillance Specification 4.11.1.3.1 was requested to be changed to reflect that dose projections are not required for liquid effluents which have been processed by the Liquid Radweste Treatment System prior to being discharged. Similarly, the request would clarify Surveillance Specification 4.11.2.4 to reflect that dose pro-jections are not required for gaseous effluents which have been pro-cessed by the Gaseous Redweste Treatment System prior to being released.
The clarifications sought by the licensee are consistent with the Consiission's original intent to require dose projection due to' liquid or gaseous releases only when untreated effluents are to be discharged, l
.. and with the intent of the Comission's model Radiological Effluent Technical Specifications (RETS) for PWRs NUREG-0472. Revision 2 February 1, 1980. Thus, we find the changes to be a hinistrative and acceptable.
ENVIRONIENTAL CONSIDERATION These amenhents involve a change in use of facility components located within the restricted area as defined in 10 CFR Part 20 and change surveillance requirements. The staff has detemined that the amendnents involve 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 cumulative occupational radiation exposure. The Comission has previously issued a proposed finding that these amendments involve no significant hazards consideration, and there has been no public coment on such finding.
Accordingly, the amendments meet the eligibility criteria for cate-goricalexclusionsetforthin10CFRSection51.22(c)(9). Pursuant to 10 CFR 51.22(b) no environmental assessment need be prepared in connection with the issuance of these amendments.
IV.
CONCLU5!0N The Comission made proposed determinations that the amenhents involve no significant hazards consideration which were published in the Federal Resister on February 24,1984(4gFR7033)andAugust28, 1985 (50 FR 3e939), and consulted with the state of North Carolina.
No public coments were received, and the state of North Carolina did not have any coments.
We have concluded, based on the considerations discussed above, that:
(1) there is reasonable assurance that the health and safety of the p(ublic will not be endangered by operation in the proposed manner, and
- 2) such activities will be conducted in compliance with the Comis-sion's regulations and the issuance of these amenhents will not be inimical to the comon defense and security or to the health and safety of the public.
Principal Contributors:
D. 5. Hood, Licensing Branch No. 4, DL M. Meinke, Radiological Assessment Branch, D5!
Dated:
November 22, 1985
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November 22, 1985 AMENDMENT NO. 49 TO FACILITY OPERATING LICENSE NPF McGUIRE NUCLEAR STATION, UNIT 1 AMENDMENT NO. 30 TO FACILITY OEPRATING LICENSE NPF McGUIRE NUCLEAR STATION, UNIT 2 DISTRIBUTION:
"'DIcketNos. 50-369/370 NRC PDR Local PDR NSIC LB 44 r/f E. Adensan D. Hood M. Duncan Attorney, OELD R. Dig 9s, ADM J.Bagart(8) nwn,..., -
E. L. Jordan, DE0A:l&E L. J. Harmon, !&E File (2)
- 8. Grimes J. Partlow M. Virgilio M. Schoppman. LOB F. Allenspach, LQB M. Meinke, RAB
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