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Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20211G9631999-08-30030 August 1999 SER Accepting Licensee Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves ML20196J2191999-06-30030 June 1999 SER Concluding That Licensee USI A-46 Implementation Program,In General,Met Purpose & Intent of Criteria in GIP-2 & Staff Sser 2 for Resolution of USI A-46 ML20207G6411999-06-0303 June 1999 Safety Evaluation Supporting Amends 105,235 & 171 to Licenses DPR-21,DPR-65 & NPF-49,respectively ML20206M4631999-05-11011 May 1999 Safety Evaluation Supporting Alternative Proposed by Licensee to Perform Ultrasonic Exam on Inner Surface of Nozzle to safe-end Weld ML20206G6221999-05-0404 May 1999 SER Accepting Util Request to Apply leak-before-break Status to Pressurizer Surge Line Piping for Millstone Nuclear Power Station,Unit 2 ML20204H7131999-03-17017 March 1999 Safety Evaluation Concluding That NNECO Provided Adequate Justification for Deviations from RG 1.97,Rev 2, Recommendations,For Instrumentation Monitoring CST Level & Containment Area Radiation at Mnps Unit 2 ML20204C9441999-03-10010 March 1999 Safety Evaluation Denying Licensee Request for License Amend to Revise Frequency of Certain SRs for Electrical Power Sys ML20207L2631999-03-0505 March 1999 Safety Evaluation Supporting Amend 104 to License DPR-21 ML20207L5961999-02-22022 February 1999 Safety Evaluation Concluding That Code Requirements,Which Require 100 Percent Volumetric Exam of RPV flange-to-shell, Impractical to Perform to Extent Required & That Alternative Provide Reasonable Assurance of Structural Integrity ML20203D7601999-02-11011 February 1999 Safety Evaluation Supporting Millstone 1 Certified Fuel Handler Training & Retraining Program ML20196B0501998-11-24024 November 1998 Safety Evaluation Re Licensee 960213 Submittal of 180-day Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Plant,Unit 2 ML20155K1981998-11-0909 November 1998 Safety Evaluation Re Application of leak-before-break Status to Portions of Safety Injection & Shutdown Cooling Sys ML20195B8711998-11-0909 November 1998 Safety Evaluation Approving Revised Evaluation of Primary Cold Leg Piping leak-before-break Analysis for Plant ML20155C3781998-10-30030 October 1998 SER Denying Amend to Allow Changes to Fsar.Nrc Found That NNECO Had Not Considered Diversity Provided by Switch in Control Room That Removes Power to 1 of 2 MOV in SDC Sys Flow Path in Evaluation of High Low Pressure Design ML20155C8441998-10-29029 October 1998 Safety Evaluation Accepting Licensee Proposal to Withdraw ATWS Test Commitment ML20238F2781998-08-27027 August 1998 SER Related to Proposed Rev 20 to Northeast Utilities Quality Assurance Program Topical Rept for Millstone Nuclear Power Station,Units 1,2 & 3 ML20237D5001998-08-20020 August 1998 SER Approving Code Case N-389-1, Alternative Rules for Repairs,Replacements,Or Mods,Section Xi,Div 1 ML20236U7051998-07-22022 July 1998 Safety Evaluation Granting All Requests for Relief W/Exception of Requests RR-89-17 (Authorized for Class 1 Sys Only) & RR-89-21.Requests RR-13 & RR-14 Will Be Addressed in Separate Evaluation ML20236K6971998-07-0101 July 1998 SER Accepting Third 10-year Interval Inservice Insp Program Plan,Rev 2 & Associated Request for Relief & Proposed Alternatives for Plant,Unit 2 ML20236K3531998-07-0101 July 1998 Safety Evaluation Supporting Amend 218 to License DPR-65 ML20249C2541998-06-24024 June 1998 Safety Evaluation Accepting Proposed Rev 19 to NNECO QAP Topical Rept & Amended Through 980609.Informs That NNECO Exception to Provisions in Paragraph 10.3.5 of Constitutes Temporary & Acceptable Alternative ML20248J0031998-06-0404 June 1998 Safety Evaluation Accepting Millstone Nuclear Power Station Emergency Plan ML20248M2991998-06-0202 June 1998 Safety Evaluation Approving Application Re Restructuring of Central Maine Power Co by Establishment of Holding Company ML20248C4131998-05-26026 May 1998 SER of Individual Plant Exam of External Events Submittal on Millstone Nuclear Power Station,Unit 3 ML20217M4181998-04-30030 April 1998 Suppl Safety Evaluation Accepting Licensee RCS Pressure & Heat Removal by Containment Heat Removal Sys post-accident Monitoring Instrumentation ML20216G7921998-03-13013 March 1998 Safety Evaluation Authorizing Proposed Alternative to Check Valve Obturator Movement Requirements of OM-10 for SIL Accumulator Outlet for Listed Check Valves ML20203E8521998-02-17017 February 1998 SER Accepting Request for Relief from Requirements of 10CFR50.55a(f) for Performing Required Inservice Testing of Certain Class 2 Components IAW ASME Boiler & Pressure Vessel Code Section XI for Plant,Unit 3 ML20203E9341998-02-17017 February 1998 SER Accepting Request for Relief from Requirements of 10CFR50.55a(g) for Performing Required Exams for Certain Class 1 Components IAW ASME Boiler & Pressure Vessel Code Section XI for Plant,Unit 3 ML20203E2441998-02-0909 February 1998 Safety Evaluation Accepting Re Approval of Realistic,Median Centered Spectra Generated for Resolution of USI-A-46 ML20198R9941998-01-13013 January 1998 SER Accepting Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Millstone Nuclear Power Station,Unit 3 ML20202H7461997-12-10010 December 1997 Safety Evaluation Accepting Licensee Position That Correction of AC-11 Single Failure Vulnerability Unncessary ML20202J0911997-12-0202 December 1997 Safety Evaluation Accepting Proposed Exemption,Which Meets Special Circumstance Given in 10CFR50.12(a)(2)(ii) ML20198S2411997-10-31031 October 1997 SE Accepting Licensee Request for Deviations from Recommendations in Reg Guide 1.97,Rev 2 for Temp & Flow Monitoring Instrumentation for Cooling Water to ESF Sys Components & Containment Isolation Valve Position ML20212G5991997-10-27027 October 1997 Safety Evaluation Supporting Amend 103 to License DPR-21 ML20217K8801997-10-27027 October 1997 Correction to Safety Evaluation Supporting Amend 103 to License DPR-21.Phrase or Rod Block Protection Has Been Deleted from Listed Sentence in Staff Associated SE ML20212F1381997-10-22022 October 1997 Safety Evaluation Supporting Amend 102 to License DPR-21 ML20217M9301997-08-19019 August 1997 Safety Evaluation Accepting Continued Operation W/O High Startup Rate Trip by Nene for Millstone,Unit 2 ML20149J2661997-07-23023 July 1997 Safety Evaluation Accepting Changes & Reanalyses in ECCS Evaluation Models & Application of Models for Plant,Unit 2 ML20141L8821997-05-28028 May 1997 Safety Evaluation Supporting Amend 101 to License DPR-21 ML20138A0111997-04-23023 April 1997 Safety Evaluation Accepting Licensee Proposal,Not to Perform Type C Leakage Rate Testing on 14 Subject CIVs ML20137V5931997-04-15015 April 1997 Safety Evaluation Supporting Amend 100 to License DPR-21 ML20137U3121997-04-10010 April 1997 Safety Evaluation Supporting Amends 99,206 & 135 to Licenses DPR-21,DPR-65 & NPF-49,respectively ML20134A0331997-01-23023 January 1997 Safety Evaluation Accepting Util Proposed Alternatives to ASME Code Requirements ML20133N3401997-01-14014 January 1997 Safety Evaluation Supporting Amend 98 to License DPR-21 ML20135C4221996-12-0202 December 1996 Safety Evaluation Accepting Proposed Alternative Described in Relief Request R-1 Re Valve Inservice Testing Program at Facility ML20128P4381996-10-0909 October 1996 Safety Evaluation Accepting Review of Cracked Weld Operability Calculations & Staff Response to NRC Task Interference Agreement ML20128L7541996-10-0404 October 1996 Safety Evaluation Supporting Amend 97 to License DPR-21 ML20248C5451995-05-0202 May 1995 SER on Millstone Unit 3 Individual Plant Exam of External Events to Identify plant-specific Vulnerabilities,If Any,To Severe Accidents & Rept Results Together W/Any licensee-determined Improvements & C/A to Commission ML20248C5731994-07-19019 July 1994 SER Step 1 Review of Individual Plant Exam of External Fire Events for Millstone Unit 3 ML20059H4991994-01-24024 January 1994 Safety Evaluation Accepting Revised Responses to IEB-80-04 Re MSLB Reanalysis 1999-08-30
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217P5391999-10-25025 October 1999 Rev 0,Change 1 to Millstone Unit 1 Northeast Utils QA Program ML20217C8721999-10-0606 October 1999 Rev 21,change 3 to MP-02-OST-BAP01, Nuqap Topical Rept, App F & G Only B17896, Monthly Operating Rept for Sept 1999 for Millstone Nuclear Power Station,Unit 1.With1999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Millstone Nuclear Power Station,Unit 1.With B17894, Monthly Operating Rept for Sept 1999 for Millstone Nuclear Power Station,Unit 2.With1999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Millstone Nuclear Power Station,Unit 2.With B17898, Monthly Operating Rept for Sept 1999 for Millstone Nuclear Power Station,Unit 3.With1999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Millstone Nuclear Power Station,Unit 3.With ML20216J4341999-09-24024 September 1999 Mnps Unit 3 ISI Summary Rept,Cycle 6 ML20211N8401999-09-0202 September 1999 Rev 21,change 1 to Northeast Utils QA TR, Including Changes Incorporated Into Rev 20,changes 9 & 10 B17878, Monthly Operating Rept for Aug 1999 for Mnps,Unit 1.With1999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Mnps,Unit 1.With B17874, Monthly Operating Rept for Aug 1999 for Millstone Nuclear Power Station,Unit 3.With1999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Millstone Nuclear Power Station,Unit 3.With ML20216F5141999-08-31031 August 1999 Rept on Status of Public Petitions Under 10CFR2.206 B17879, Monthly Operating Rept for Aug 1999 for Millstone Nuclear Power Station,Unit 2.With1999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Millstone Nuclear Power Station,Unit 2.With ML20211G9631999-08-30030 August 1999 SER Accepting Licensee Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves ML20211A6561999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Millstone Nuclear Power Station,Unit 2 B17858, Monthly Operating Rept for July 1999 for Millstone Nuclear Power Station,Unit 3.With1999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Millstone Nuclear Power Station,Unit 3.With B17856, Monthly Operating Rept for July 1999 for Millstone Nuclear Power Station,Unit 1.With1999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Millstone Nuclear Power Station,Unit 1.With ML20210J0311999-07-21021 July 1999 Rev 20,Change 10 to QAP 1.0, Organization ML20210E5931999-07-19019 July 1999 Revised Page 16 of 21,to App F of Northeast Util QA Program Plan ML20210C5911999-07-15015 July 1999 Revised Rev 20,change 10 to Northeast Util QA Program TR, Replacing Summary of Changes ML20210A0411999-07-15015 July 1999 Rev 20,change 10 to Northeast Util QA Program Tr B17814, Special Rept:On 990612 B Train EDG Failed to Restart within 5 Minutes Following Completion of 18 Month 24 H Endurance Run Required by TS 4.8.1.1.2.g.7.Caused by Procedural inadequacy.Re-performed Hot Restart Via Manual Start1999-07-12012 July 1999 Special Rept:On 990612 B Train EDG Failed to Restart within 5 Minutes Following Completion of 18 Month 24 H Endurance Run Required by TS 4.8.1.1.2.g.7.Caused by Procedural inadequacy.Re-performed Hot Restart Via Manual Start ML20209D1881999-07-0101 July 1999 Rev 20,change 9 to Northeast Util QA Program Tr ML20196J2191999-06-30030 June 1999 SER Concluding That Licensee USI A-46 Implementation Program,In General,Met Purpose & Intent of Criteria in GIP-2 & Staff Sser 2 for Resolution of USI A-46 ML20211A6751999-06-30030 June 1999 Revised Monthly Operating Rept for June 1999 for Millstone Nuclear Power Station,Unit 2,providing Revised Average Daily Unit Power Level & Operating Data Rept ML20196A8451999-06-30030 June 1999 Post Shutdown Decommissioning Activities Rept ML20209J0541999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Millstone Unit 2 B17830, Monthly Operating Rept for June 1999 for Millstone Nuclear Power Station,Unit 3.With1999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Millstone Nuclear Power Station,Unit 3.With ML20196K1791999-06-30030 June 1999 Addendum 6 to Millstone Unit 2 Annual Rept, ML20196J1821999-06-30030 June 1999 Rev 21,Change 0 to Northeast Utilities QAP (Nuqap) Tr B17833, Monthly Operating Rept for June 1999 for Millstone Power Station,Unit 1.With1999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Millstone Power Station,Unit 1.With ML20195H1011999-06-11011 June 1999 Rev 20,change 8 to Northeast Utilities QAP (Nuqap) TR ML20207G6411999-06-0303 June 1999 Safety Evaluation Supporting Amends 105,235 & 171 to Licenses DPR-21,DPR-65 & NPF-49,respectively ML20211A6631999-05-31031 May 1999 Revised Monthly Operating Rept for May 1999 for Millstone Nuclear Power Station,Unit 2,providing Revised Average Daily Unit Power Level,Operating Data Rept & Unit Shutdowns & Power Reductions B17808, Monthly Operating Rept for May 1999 for Millstone Nuclear Power Station,Unit 3.With1999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Millstone Nuclear Power Station,Unit 3.With ML20211B7351999-05-31031 May 1999 Cycle 7 Colr B17804, Monthly Operating Rept for May 1999 for Mnps,Unit 2.With1999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Mnps,Unit 2.With B17807, Monthly Operating Rept for May 1999 for Mnps,Unit 1.With1999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Mnps,Unit 1.With ML20209J0661999-05-31031 May 1999 Revised Monthly Operating Rept for May 1999 for Millstone Unit 2 ML20206M4631999-05-11011 May 1999 Safety Evaluation Supporting Alternative Proposed by Licensee to Perform Ultrasonic Exam on Inner Surface of Nozzle to safe-end Weld ML20206J8351999-05-0707 May 1999 Rev 20,Change 7 to QAP-1.0, Northeast Utls QA Program (Nuqap) Tr ML20206G6221999-05-0404 May 1999 SER Accepting Util Request to Apply leak-before-break Status to Pressurizer Surge Line Piping for Millstone Nuclear Power Station,Unit 2 B17782, Monthly Operating Rept for Apr 1999 for Millstone Nuclear Power Station,Unit 1.With1999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Millstone Nuclear Power Station,Unit 1.With ML20205R3531999-04-30030 April 1999 Addendum 4 to Annual Rept, B17775, Monthly Operating Rept for Apr 1999 for Millstone Nuclear Power Station Unit 3.With1999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Millstone Nuclear Power Station Unit 3.With ML20205K6141999-04-30030 April 1999 Non-proprietary Version of Rev 2 to Holtec Rept HI-971843, Licensing Rept for Reclassification of Discharge in Millstone Unit 3 Spent Fuel Pool ML20206E2971999-04-30030 April 1999 Rev 1 to Millstone Nuclear Power Station,Unit 2 COLR - Cycle 13 B17777, Monthly Operating Rept for Apr 1999 for Millstone Unit 2. with1999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Millstone Unit 2. with ML20205Q5891999-04-0909 April 1999 Rev 20,change 6 to QAP-1.0,Northeast Utils QA Program TR ML20205R8751999-04-0909 April 1999 Provides Commission with Staff Assessment of Issues Related to Restart of Millstone Unit 2 & Staff Recommendations Re Restart Authorization for Millstone Unit 2 ML20206T3991999-03-31031 March 1999 First Quarter 1999 Performance Rept, Dtd May 1999 B17747, Monthly Operating Rept for Mar 1999 for Millstone Nuclear Power Station,Unit 1.With1999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Millstone Nuclear Power Station,Unit 1.With 1999-09-30
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-$ELATEDTODEGRADEDGRIDVOLTAGEPlOCE00RES j 4
D NORTHEAST NUCLEAR EhERGY COMPANY HILLSTONE NUCLEAn. POWER STATION, UfeIT NO _ . '
, DgCKETNO.50-245 ;
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1.0 INTRODUCTIO,N ,
- During nurmalp' lant operation, the safety class IE pawer distribution busses are supplied electrical power by the plant's main turbine generator through 1
the normal station service trar.sformftr. Power can also be supplied to the safety class IE di$tribution busses from the off-site transmission grid Vis the r.eserve station service transfomer. When off-site power is not -
-availabie, redundant emergency generatcrs are available to supply power to the safety clast IE power di.stribution busses, 7
P A degraded gr'id voltage condition occurred at Millst ne Nuclear Power istation on July 5, 1976 that caused coimonent failures in the class.1E electric system af Unit 2. The staff requestad (see refere.nced) that the license'a analyze the class IE systems to determine the grid voltage at which damage could of. cur. As a recilt, the li;ensee made plans to install vsltage sensing devices on the class lE busses with coincident logic and with the low voltage set points abova values where equipment
' damage could occbr. It wu planned that the vo?tage ' sensing devices would cause the off-site grid power supp'y ta be disconnected automatically from the class IE System chove voltages where the Asage could occur.
The class IE busies upon deing discennected crould then be supplied power from their respective einergency generator.
However, the licensee was cor.cerned because of the large number of nuclear plants 'in the New England area that significant degradation of the grid would result if the Millstone Unit No. I disconnection was automatic. ,
8605290374 860520 PDR ADOCK 05000245-P PDR
It was the licensco's view that automatic disconnection from the grid should only be required if a low grid voltage occurred at the seme tiine asalossofCoo?antAccideet(LOCA). Tne staff. agreed that a LOCA coincident with in degraded grid voltige candition, should cause automatic disconnect frun the of f-site grid. Iso, for a degraded grid voltage condit1on Without a LOCA, t.he operator could be relied on to take the
- necessary manual cctica to prot (ct the class 1E system.
This proposal was reviewed and acceoted by a NRC letter, dated June 23, 1982, (Reference 6) that required the licensee to develop an operatir.g procedure to provide the nececsary operator gyid3nce to protect the class iE system under degraded grid voltage conditions without a LOCA conditicn. By letter dateo Octcbar 9, 1985, the ilcentae submitted ,
for staff review a revised plant procedure to cDer aperator actions, The staff has compluted tne evaluation of this pro'edure c and the latest revision (Revision 23) made available by the licensee.
2.0 DISCUSSION The operating procedure, designed to assure protection of class IE systems under degraded grid voltage conditions without a concurrent LOCA, was reviewed during a site visit discussed in the staff's Inspection Report No. 50-245/85-25.
The staff noted that, when the low voltage alarm signals 345KV on the reserve station service transformer primary, the operator:
Requests Connecticut Valley Electric Exchango (CONVEX) to raise the system voltage above 345KV. If unit 1 is supplying power via the 4.16KV system to Unit 2, the voltage request would be for 347KV. If the 345KV or 347KV requirement cannot be met, the operator notifies the Duty Officer.
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If the voltage cannot be raised above the alarm point or the main generator current is greater than 17.5 Kiloamps, the operator:
- Notifies CONVEX that reactor power is being reduced until the generator current is normal. The power reduction, about 10%, is accomplished by reducing the speed of the recirculation pumps.
- Starts the emergency gas turbine and diesel generator and lets them idle if after the above reduction the 345KV system voltage does not return to normal. (Theemergency generator start provisio.n has since been changed; and is discussed below in the evaluation.)
- Monitors buss voltage on 4.16KV class 1E busses. If the voltage drops to 3646 volts on any two busses, the operator notifies CONVEX that the station wants to open the Unit 1 main generator breaker at the 345KV switchyard.
Opens the main steam bypass valves about 10% using the speed load changer prior to opening the main generator breaker.
Opens the breakers and adjusts the generator speed and excitation after CONVEX permission.
When the station electrical service is being supplied power from the isolated Unit 1 main generator it is not subject to the degraded grid voltage condition.
3.0 EVALUATION The operating procedure 24KV Electrical System, OP 340, Revision 21, for degraded grid ve age was revised (effective February 1, 1985) to include operatcr attention to the fact that alarms also may be received from new sensors on 4.16KV busses 14A,148,14C and 140. These alarias are identified in opert. ting procedure 4160 volt Electrical System,
OP 341, Revision 13 (effective February 1,1985). The operator monitors the voltage of the above busses. The operator action of starting the emergency gas turbine and the diesel generator has been changed in Revision 23, OP 340, effective December 10, 1985. The gas turbine only will be started. The diesel generator will not be started until needed because unloaded operation is restricted to less than 5 minutes dura tion.
The class IE motors' design voltage is 4000 volts. These motors can operate continuously with a ten percent voltage reduction without insulation degradation or life reduction. This reduced voltage, accounting for cable 4.16 voltage drop, measured at the 4.16KV busses is 3646 volts. Should a degraded grid voltage occur, the operator would take corrective action when any two of the four 4.16KV busses voltmeters indicate 3646 volts. The corrective action, opening the main generator breaker, separates the generator from the degraded grid voltage condition. The main generator, then isolated from the grid, supplies power to the motors rated at 4000 volts. Thus, during a degraded grid voltage condition the class 1E motors would not be operated beyond their rated voltage limits and will meet their intended safety function. The procedure provides the operator with guidance to meet this safety objective.
4.0 CONCLUSION
-The staff concluded, based on the consideration discussed above, that:
- 1. The operating procedure, OP 340, Revision 23, provides an acceptable means for operator action to protect the Class 1E electrical system during a degraded grid voltage condition without a coincident LOCA condition.
- 2. There is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner.
5-References
- 1. Reportable Occurrence Report 76-42/IP, July 5, 1976, Millstone Unit 2 Degraded Grid Voltage and Related Event On July 21, 1976.
- 2. Licensee Event Report 76-42/IT, August 3, 1976, same subject as 1.
- 3. G. Lear letter to D. C. Switzer, dated June 2,1977.
- 4. D. M. Crutchfield letter to W. G. Counsil, dated November 24, 1981.
- 5. W. G. Counsil letter to D. M. Crutchfield, dated April '21,1982.
- 6. D. M. Crutchfield letter to W. G. Counsil, dated June 23, 1982.
- 7. J. Shea letter to W. G. Counsil, dated June 30, 1982.
- 8. Integrated Plant Safety Assessment, NUREG-0824, Millstone Nuclear Power Station, Unit No.1, Final Report, February 1983.
i
- 9. W. G. Counsil letter to D. M. Crutchfield, dated January 17, 1984.
- 10. W. G. Counsil letter to D. M. Crutchfield, dated April 26, 1984.
- 11. J. R. Miller letter to W. G. Counsil, dated April 27, 1984,
- 12. W. G. Counsil letter to D. M. Crutchfield, dated May 11, 1984.
- 13. W. G. Counsil letter to J. R. Miller, dated June 11, 1984.
- 14. J. F. Opeka letter to C. I. Grimes, dated May 17, 1985.
6-
- 15. H. Le Tho:npson letter to J. F. Opek:, dated July 31, 1985.
- 16. J. F. Opeka letter to C. I. Grimes, dated October 9, l'385.
- 17. S. D. Ebneter letter to J F. Opeka, dated November 26, 1985, ,
Dated: K1y 20,1986 Principal Contributor: Frederick 9. Paulitz Division of Reect.or Safety, Region i L
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