ML20040A686
| ML20040A686 | |
| Person / Time | |
|---|---|
| Site: | McGuire  |
| Issue date: | 12/31/1981 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20040A684 | List: |
| References | |
| NUDOCS 8201210415 | |
| Download: ML20040A686 (3) | |
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SAFETY EVALUATI0ll BY THE OFFICE OF t!UCLEAR REACTOR REGULATI0'l RELATED TO N1ENDtiENT NO.10 TO LICENSE NPF-9 DUKE PouER C0tiPANY INTRODUCTIGH By letters dated Novsber 11, 1981 and December 16, 1981, the licensee requested changes to the McGuire Huclear Station Unit 1, License NPF-9, License Conditions:
(a) 2.C.(11)f.(1) - Inadequate Core Cooling Instrunents (II.F.2); reactor vessel water level instrumentation systen (b) 2.C.(11)f.(3) - Inadequate Core Cooling Instrunents (II.F.2); in-core thernoccuple nonitoring systen.
(c) 7.C.(11)l.(2) - Final Recomnen.iations of B & 0 Task Force (II.K.3);
revised small break LOCA model (II.K.3.30)
The proposed changes involve extending the required implementation dates for three NUREG-0737 condition items.
EVALUATIGH Pursuant to the Tl'l-related action items described in HUPIG-0737, " Clarification of THI Action Plan Requirenents" which were approved by the Conmission for inple-nentation, the McGuire Unit 1 operating license is conditioned to the extent that the aforenentioned license conditions each have a January 1,1982 implementation date.
Condition (a)
In its letter of Novenber 11, 1981, requesting a change in the license condition innlenentation date from January 1,1982 to prior to startup af ter the first refueling, the licensee stated that considerable effort has been taken to install the Westinghouse Reactor Vessel Level Instrunentation Systen (RVLIS). All installation work not requiring shutdown of the unit has been completed. During the recent unscheduled outage which comnenced in early Decenber, vacuum fill and hydraulic balancinq of the system was started. The final installation and check-out of the systen will, however, require an additional outage period of approx-imately 6 weeks.
It is not anticipated that such an outage during the near term will be available. Based on the licensee's ef forts to date we consider that the licensee has made cood faith efforts to meet the schedule date of January 1,1982.
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. The staff has not yet coaipleted its review of the design of the Westinghouse level system. Also the staff has previously evaluated this matter and granted a sinilar extension to the Sequoyah Huclear Station Unit 2 to install the RVLIS prior to startup after the first refueling. The staff does not consider the requested extension to represent a safety concern and is consistent with the decision already accepted by the Commission.
Condition (b)
By letter dated December 16, 1981, the licensee requests a change in the license condition implementation date from January 1,1982 to prior to startup after the first refueling. This condition requires the incore thermocouple system to meet a revised set of design criteria in the areas of perforpance, qualification and operator interface. In a letter to the NRC on April 23, 1981, the license pro-vided its assessment of the installed thermocouple systen and stated its intent to pursue development of a therroccuple system which would neet the criteria in NUREG-0737. Toward this end the licensee has completed the following:
(1) Requested a proposal from Westinghouse for an upgraded system (2) Evaluated the separation of thermocouple cables fcr complian'e with 10 CFR 50 Appendix R (Ref: Licensee letter dated October 21, 1981 to the NRC)
(3) Evaluated the survivability of the cables associated with the incore (core exit) thermocouples (Ref: " Analysis of Hydrogen Control Measures at McGuire Nuclear Station", Section 5.0,
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subnitted to the NRC on October 31,1981.)
(4)
Increased the range of the backup display to 2300 F from the original 700 F.
A final design has yet to be developed by Westinghouse as a resolution to this generic requirement. Based on the licensee's efforts to date we consider that the licensee has made good faith ef forts to meet the schedule date of January 1, 1982. Although the staff has yet to evaluate the submitted information, it has no basis to rescind its approval of the themocouple monitoring systen as pre-sently installed at McGuire and concludes that deferral of the required inple-mentation date will not result in a reduction in safety. As in the case of Condition (a), we have granted a similar deferral to the Sequoyah Nuclear Station, Unit 2 and this action is consistent with the decision already accepted by the Cormission.
l Condition (c)
This condition requires that the analysis methods used by Westinghouse for small-break LOCA analysis for compliance with Appendix K to 10 CFR Part 50 be revised OFFICIk SURNAMEf DATEf NRCFORM 318 (10,001 NRCM O240 OFFICIAL RECORD COPY
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-a-docurented, and submitted for 4RC approval. By letter dated December 16, 1981, the licensee requosts a change in the license condition submittal date from January 1,1982 to May 1,1982.
In its letter of Decenber 16, 1981, the licensee states that the small-break LOCA analysis nodel currently approved by the NRC for use on McGuire Nuclear Station is conservative and in conformance with Appendix K to 10 CFR Part 50.
However, (as documented in letter NS-Tt'A-2318, dated September 26, 1930, T. M. Anderson to D. G. Eisenhut) Westinghouse believes that improvement in the realism of small-break calculations is a worthwhile effort and has com-m'tted to revise its small-break LOCA analysis nodel to address NRC concerns (e.g. NOREG-0611, HUREG-0623, etc. ) requiring further analysis. This revised Westinghouse rodel is currently scheduled for submittol to the NPC by April 1, 1082 as documented in letter US-EPP-PC?4, dated November 25, 1981, E. P. Rahe to D. G. Eisenhut. Based coon the licensee's efforts to date we consider that the licensee has made gon.i faith efforts to meet the schedule date of January 1, 1982.
Until the staff has evaluated the revised nodel it has no basis to rescind its approval of the current nodel and concludes that deferral of the required inple-mentation date will not result in a reduction in safety. As in the previously discussed Conditions, we have granted a similar deferral to the Sequoyah Nuclear Station Unit 2.
ENVIPONMENTAL CONS 10 ERAT 104 We have deternined that the arendment does not authorize a change in effluent types or total amounts nor an increase in power level and will not result in any sianificant environmental innact. Having nade this determination, we have further concluded that the amendnent involves an action which is insignificant from the standpoint of environmental impact and, pursuant to 10 CFR Section 51.5(d)(4), that an environnental impact statement or negative declaration and environmental impact appraisal need not he prepared in connection with the issuance of this anendment.
COMCLUSION We have concluded, based on the consideration discussed above, that: (1) because the amendment does not involve a significant increase in the probability or con-sequences nf accidents previously considered and does not involve a significant decrease in a safety margin, the amendment does not involve a significant hazards consideration, (2) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed nanner, and (3) such activities will be conducted in compliance with the Commission's regulations and i
the issuance of this amendment will not be inimical to the common defense and security or to the bealth and safety of the public.
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SAFETY-EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMEMDMENT HO. 10 TO LICENSE NPF-9 DUKE POWER COMPANY i
INTRODUCTION By letters dated Noveirber 11, 1981 and Dece:Wer 16, 1981, the licensee requested changes to the McGuire Muclear Station Unit 1, License NPF-9, License Conditions:
(a) 2.C.(11)f.(1) - Inadequate Core Cooling Instrunents (II.F.2); reactor vessel water level instrumentation system (b) 2.C.(11)f.(3) - Inadequate Core Cooling Instruments (II.F.2); in-core thervocouple monitoring system.
(c) 2.C.(11)l.(2) - Final Recoranendations of B & 0 Task Force (II.K.3);
revised small break LOCA model (II.K.3.30) t The proposed changes involve extending the required impleaentation dates for three NUREG-0737 condition item.
EVALUATION Pursuant to the THI-related action items described in NUREG-0737, " Clarification of TMI Action Plan Require:nents" which were approved by the Comission for irple-r..entation, the McGuire Unit 1 operating license is conditioned to the extent that the aforementioned license conditions each have a January 1,1982 icplenentation date.
f Condition (a)
In its letter of Novenhor 11, 1981, the licensee stated that considerable effort I
has been taken to install the Westinghouse Reactor Vessel Level Instruentation Systeu (RVLIS). All work not requiring shutdoun of the unit has been completed.
During the recent unscheduled cutase which comenced in early Dece:ter, vacuum j
fill and hydraulic balancing of the system was started.
The final installation and checkout of the system will, however, require an additional outage period of approximately 6 weeks.
It is not anticipated that such an outage during the l
near term will be available.
In addition the staff has not yet compic 'd its revleu of the design of the Westinghouse level system.
The taff % s-no con-j j
sider the requested extension to represent a safety concern Relatedly th staff g,g %r#
l has previously evaluated this matter and granted a sir.iilar ex nsion-ttrtne Sequoyah Nuclear Station, Units 1 and 2.
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Condition (b)
This condition requires the incore thernoccuple system to meet a revised set of l
design criteria in the areas of performance, qualification and operator inter-face.
In a letter to the NRC on April 23, 1981, the license provided its assess-ment of the installed thenroccuple system and stated its intent to pursue develop-i ment of a thenrocouple systen which would meet the criteria in fluREG-0737. Toward this end the licensee has coapleted the following:
(1) Requested a proposal from Westinghouse for an upgraded system (2) Evaluated the separation of thermocouple cables for cor@liance with 10 CFR SO Appendix R (Ref: License letter dated October 21, 1981 to the NRC)
(3) Evaluated the survivability of the cables associated with the incore (core exit) thermocouples (Ref: " Analysis of !!ydrogen l
Control itcasures at McGuire lluclear Station", Section 5.0, submitted to the NRC on October 31,1981.)
(4)
Increased the range of the backup display to 2300 F from the original 700"F.
A final design has yet to be developed by Westinghouse as a resolution to this generic requirement. Although the staff has yet to evaluate the submitted infonnation, it has no basis to rescind its approval of the thermocouple monitoring syste.n as presently installed at McGuire and concludes that deferral of the required i::plecentation date will not result in a reduction in safety.
As in the case of Condition (a), we have granted a similar deferral to the Sequoyah fluclear Station.
Condition (c)
This condition requires that the analysis methods used by Westinghouse for small-break LOCA analysis for cocpliance with Appendix k to 10 CFR Part 50 be revised, documented, and submitted for NRC approval.
In its letter of flovember 16, 1981, the licensee states that the sv.all-break LOCA analysis model currently approved by the HRC for use on f*cCuire Nuclear Stetion is conservative and in confor;cance with Appendix K to 10 CFR Part 50.
I However, (as documented in letter !!S-TiiA-2318, dated September 26, 1980, T. M. Anderson to D. G. Eisenhut) Mestinghouse believes that inprovement in the realism of small-break calculations is a worthwhile effort and has coa-mitted to revise its small-break LOCA analysis model to address URC concerns t
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. HUREG-0611. HUREG-C523, etc.) This revised Westinghouse model is cur-l rently scheduled for submittal to the HRC by April 1,1932 as documented in l
letter NS-EPR-2524, dated November 25, 1981, E. F. Rahe to D. G. Eisenhut.
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! Until the staff has evaluated the revised model it has no basis to rescind its approval of the current nodel and concludes that deferral of the required imple-mentation date will not result in a reduction in safety. As in the previously discussed Conditions, we have granted a similar deferral to the Sequoyah Nuclear Station.
ENVIRONME!4TAL CONSIDERATI0il We have determined that the auendment does not authorize a change in effluent types or total ar.ounts nor an increase in power level and will not result in any significant environaental impact. Itaving trade this deterr.11 nation, we have further concluded that the amendr,ent involves an action which is insignificant from the standpoint of environmental impact and, pursuant to 10 CFR Section 51.5(d)(4), that an environacutal inpact statement or negative declaration and environnental ti. pact appraisal need not be prepared in connection with the issuance of this aa.endment.
LONCLUSION Ue have concluded, based on the consideration discussed above, that: (1) because the amndment does not involve a significant increase in t.he probability or con-sequences of accidents previously considered and does not involve a significant decrease in a safety margin, the amendment does not involve a significant hazards consideration, (2) there is reasonable assurance that the health and safety of the public uill not be endangered by operation in the proposed manner, and (3) such activities will be conducted in cocpliance with the Comission's regulations and the issuance of this amendaunt will not be inimical to the comon defense and security or to the health and safety of the public.
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