ML20093D176

Forwards Update to Schedule & Implementation Status of TMI Action Items in NUREG-0737

ML20093D176
Person / Time
Site:	Point Beach
Issue date:	07/09/1984
From:	Fay C WISCONSIN ELECTRIC POWER CO.
To:	Harold Denton Office of Nuclear Reactor Regulation
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-***, TASK-TM GL-82-33, GL-83-10C, GL-83-10D, GL-83-22, NUDOCS 8407160161
Download: ML20093D176 (38)

Text

\%SC0nSin Electnc powra coupasr 231 W. MICHIGAN, P.O. BOX 2046. MILWAUKEE, WI 53201 July 9,1984 Mr. Harold R. Denton, Director Office of Nuclear Reactor Reculation U.S. Nuclear Regulatory Comission Washington, D.C. 20555

Dear Mr. Denton:

D0CKET NOS. 50-266 AND 50-301 UPDATE TO THE SCHEDULE AND IMPLEMENTATION STATUS OF NUREG-0737 POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 This letter provides a sumary of the current status of our imple-mentation of NUREG-0737, " Clarification of TMI Action Plan Requirements."

There are no new schedular comitments in this letter, only a status of past comitments and a summary of the current implementation schedule.

With the exception of the current status of some items and some of the information in Notes II.F.2.1 and II.F.2.3, all of the information in this letter, including the implementation schedule, has been provided in various earlier submittals. The purpose of this letter is to ensure the NRC and Wisconsin Electric agree on which items are outstanding in our TMI Action Plan.

Your review of this letter should be made with reference to the similar Wisconsin Electric submittals of December 23, 1980, March 31 and September 14, 1981, and April 26, 1982. As in those previous submittals, we have not repeated the pertinent notes referenced in the Schedule Table for those items whose status has not changed since the April 26, 1982 letter.

One difference between this letter and the April 26 submittal occurs in the "NRC Implementation Schedule" column of the Schedule Table. For those items which we believe the NRC has closed or resolved, we have written " closed" and, in parentheses, listed the reference number of the letter which closed or resolved the item. The references are listed at the end of the enclosed Schedule Table and Notes.

If you have any questions regarding the schedule or accompanying notes, we would be pleased to answer them.

Very truly y p,

& 9 Vice Presid nt-Ndclear Power C. W. Fay Enclosures Copy to NRC Resident Inspector 8407160161 B40709 f I I PDR ADOCK OS000266 P PDR

Revision 4 July 9, 1984 REFERENCES l

1. S. Burstein (WE) letter to H. R. Denton (NRC), December 31, 1979,

" Implementation of NUREG-0578"

2. C. W. Fay (WE) letter to H. R. Denton (NRC), March 14, 1980, "Implemen-tation of NUREG-0578"

3. A. Schwencer (NRC) letter to S. Burstein (WE), April 9, 1980, " Evaluation

of Compliance with Category "A" Lessons Learned Requirements" 3a. D. G. Eisenhut (NRC) letter To All Operating Reactor Licensees, May 7, 1980, "Five Additional TMI-2 Related Requirements (Applicable) to j Operating Reactors" 3b. C. W. Fay (WE) letter to H. R. Denton (NRC), May 2, 1980, "Implementa-tior. of NUREG-0578"

4. C. W. Fay (WE) letter to H. R. Denton (NRC), June 11, 1980, "Implementa-tion of Five Additional TMI-2 Related Requirements" l

l 4a. C. W. Fay (WE) letter to H. R. Denton (NRC), July 8,1980, " Additional

Information Auxiliary Feedwater System" i 4b. D. G. Eisenhut (NRC) letter To All Licensees of Operating Plants and i

Applicants for Operating Licenses and Holders of Construction Permits, July 31, 1980, " Interim Criteria for Shift Staffing" 1

4c. C. W. Fay (WE) letter to H. R. Denton (NRC), August 7, 1980, "Qualifica-l tion of Reactor Operators"

5. C. W. Fay (WE) letter to H. R. Denton (NRC), November 3, 1980, " Status l of Duty and Call Technical Advisor Training"

6. C. W. Fay (WE) letter to H. R. Denton (NRC), December 1,1980, " Revised Emergency Plan"

7. C..W. Fay (WE) letter to H. R. Denton (NRC), November 3, 1980, " Operating

Licenses DPR-24 and DPR-27 Interim Criteria for Shift Staffing" i 8. C. W. Fay (WE) letter to H. R. Denton (NRC), September 22, 1980, i

" Comments on Draft NUREG-0696, Functional Criteria for Emergency

l. Response Facilities"

9. S. Burstein (WE) letter to H. R. Denton (NRC), October 20, 1979,

" Implementation of NUREG-0578"'- including TMI Accident Review Task Force Report (Section 3.6.A) i 9a. P. F. Collins (NRC) letter to C. W. Fay (WE), October 28, 1980, regarding j Item I.A.2.1.3 of NUREG-0737.

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Revision 4 July 9, 1984

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i 9b. R. F. Heishman (NRC) letter to Sol Burstein'(wE), November 20, 1980, Inspection Report No. 50-266/80-19 and No. 50-301/80-19.

10. R. W. Jurgensen (WOG) letter to S. H. Hanauer (NRC), OG-47, December 15, 1980, " Westinghouse Owners Group Response to Item I.C.1 of NUREG-0737" 10a. R. C. Youngdahl (EPRI) letter to D. G. Eisenhut (NRC), December 15, 1980, PWR Utilities Position on NUREG-0737, Item II.D.1, Performance Testing of BWR and PWR Relief and Safety Valves (NUREG-0778, Section 2.1.2)

11. S. H. Hanauer (NRC) letter to R. A. Newton (WE), December 17, 1980, request for a basis document for the emergency procedure guidelines.

12. C. W. Fay (WE) letter to H. R. Denton (NRC), December 23, 1980, " Response to NURG-0737, Schedule Requirements as Related to Point Beach Nuclear Plant, Units 1 and 2" 12a. R. F. Heishman (NRC) letter to Sol Burstein (WE) December 23, 1980, Inspection Report No. 50-266/80-20 and No. 50-301/80-20.

12b. C. W. Fay (WE) letter to H. R. Denton (NRC), December 30, 1980, " Point Beach Nuclear Plant Emergency Plan"

13. C. W. Fay (WE) letter to H. R. Denton (NRC), January 9,1981, " Additional Response to NUREG-0737" 13a. C. W. Fay (WE) letter to H. R. Denton (NRC), January 19, 1981, " Response to HUREG-0737"

14. R. W. Jurgensen (WOG) letter to S. H. Hanauer (NRC), OG-48, January 28, 1981, " Emergency Operating Instruction Background Documents"

15. C. W. Fay (WE) letter to H. R. Denton (NRC), February 4,1981, " Technical Specification Change Request No. 65" 15a. Sol Burstein (WE) letter to S. J. Chilk (NRC), February 18, 1981,

" Emergency Operatings Facility" 15b. D. G. Eisenhut (NRC) letter To All Licensees of Operating Plants and  ;

Holders of Construction Permits, February 18, 1981, " Post-TMI Requirements for the Emergency Operations Facility (Generic Letter 81-10)"

16. C. W. Fay (WE) letter to H. R. Denton (NRC), February 23, 1981, " Additional Responses to NUREG-0737"

17. C. W. Fay (WE) letter to H. R. Denton (NRC), February 26, 1981, " Duty and Call Technical Advisor Training" 17a. C. W. Fay (WE) . letter to H. R. Denton (NRC), February 27, 1981, " Emergency Plan Implementing Procedures"

1

, Revision 4 July 9, 1984 l

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18. C. W. Fay (WE) letter to H. R. Denton (NRC), March 4, 1981, "NUREG-0737 Schedule Requirements"

19. R. W. Jurgensen (WOG) letter to J. R. Miller (NRC), OG-52, March 13, 1981, WCAP-9804, "Probabilistic Analysis and Operational Data in Response to Item II.K.3.2 for Westinghouse NSSS Plants"

20. R. W. Jurgensen (WOG) letter to S. H. Hanauer (NRC), OG-54, March 18, 3 1981, " Westinghouse Owners Group Update on Item I.C.1 of NUREG-0737 Activities"

. 21. E. R. Mathews (WPS) letter to Sol Burstein (WE), March 19, 1981,

" Letter of Intent to Provide Mutual Assistance" j 22. C. W. Fay (WE) letter to H. R. Denton (NRC), March 31, 1981, " Emergency

Plan" l i

23. C. W. Fay (WE) letter to H. R. Denton (NRC), March 31, 1981, " Response )

to NUREG-0737 Update to Schedule Requirements and Impismentation '

i Status"

24. C. W. Fay (WE) letter to H. R. Denton (NRC), April 9,1981, " Requirements I for Auxiliary Feedwater System" t

4

25. C. W. Fay (WE) letter to H. R. Denton (NRC), April 14, 1981, " Post-TMI Requirements for the Emergency Operations Facility" 25a. R. F. Heishman (NRC) letter to Sol Burstein (WE), April 17, 1981,

regarding routine inspection conducted on March 2-31, 1981, of activities at Point Beach Nuclear Plant, Units 1 and 2.

25b. R. W. Jurgensen (WOG) letter to P. S. Check (NRC), 0G-57, April 20, 1981,

" Natural Circulation Cooldown Report"

26. C. W. Fay (WE) letter to H. R. Denton (NRC), May 7, 1981, " Containment Pressure Setpoint, NUREG-0737 Item II.E.4.2" 4

i. 26a. W. A. Wogsland (WOG) letter to L. Beltracchi (NRC), May 19, 1961,

" Proprietary Handouts, SAS Meeting, May 14, 1981"

27. D. G. Eisenhut (NRC) letter to R. W. Jurgensen (WOG), May 28, 1981, "WOG Procedures Development and Evaluation Program" l

28. Sol Burstein (WE) letter to H. R. Denton (NRC), June 1, 1981, " Emergency Response Facilities"

29. R. A. Clark (NRC) letter to Sol Burstein (WE), June 1,1981, "Clarificatiol

of Post-Accident Sampling Requirements of NUREG-0737, 11.8.3" i 30. C. W. Fay (WE) letter to H. R. Denton (NRC), June 2, 1981, " Emergency i Plan Public Notification System" l l

Revision 4 July 9, 1984

31. R. W. Jurgensen (WOG) letter to P. S. Check (NRC), OG-60, June 15, 1981, " Response to NRC Letter of May 30, 1981"

32. R. A. Clark (NRC) letter to Sol Burstein (WE), June 17, 1981, " Review of the Westinghouse Owners Group submittal for Action Plan Item I.C.1"

33. R. A. Clark (NRC) letter to Sol Burstein (WE), June 17, 1981, " Safety Evaluation by the Office of Nuclear Reactor Regulation" (RE: IEB 79-06A and 79-06A, Revision 1, Item II.K.1)

34. R. A. Clark (NRC) letter to Sol Burstein (WE), June 26, 1981, " Elimination of Item II.K.2.19"

35. C. W. Fay (WE) letter to H. R. Denton (NRC), July 6, 1981, "NUREG-0737 Schedule Update"

36. R. W. Jurgensen (WOG) letter to S. H. Hanauer (NRC), OG-61, July 7, 1981, "Sumary of WOG Program to Address NUREG-0737, Item I.C.1."

37. R. A. Clark (NRC) letter to Sol Burstein (WE), July 1C,1981, " Order Confirming Licensee Comitments on Post-TMI Related Issues"

38. C. W. Fay (WE) letter to H. R. Denton (NRC), July 17, 1981,

" Meteorological System Description"

39. R. C. Youngdahl (EPRI) letter to H. R. Denton (NRC), July 24, 1981,

" Status of EPRI PWR Safety and Relief Valve Test Program, NUREG-0737, Item II.D.1"

40. R. A. Clark (NRC) letter to Sol Burstein (WE), July 28, 1981, " Request for Additional Infornistion on Auxiliary Feedwater System"

41. R. A. Clark (NRC) letter to Sol Burstein (WE), August 5, 1981, " Westing-house Reactor Vessel Level Instrumentation for Monitoring Inadequate Core Cooling" 41a. Sol Burstein (WE) letter to S. J. Chilk (NRC), August 12,1981, "Coments on Incorporation of NUREG-0737 Licensing Requirements into 10 CFR Part 50"

42. R. A. Clark (NRC) letter to Sol Burstein (WE), August 14, 1981, "Contain-ment Isolation Pressure Setpoint"

43. R. A. Clark (NRC) letter to Sol Burstein (WE), August 19, 1981, "TMI Task Plan Items II.K.3.9, II.K.3.10, and II.K.3.12 for Point Beach Nuclear Plant, Units 1 and 2"

44. C. W. Fay (WE) letter to Secretary of the Comission (NRC), August 25, 1981, " Comments on NUREG-0799, Draft Criteria for Preparation of Emergency Operating Procedures"

Revision 4 July 9, 1984 44a. R. L. Spessard (NRC) letter to Sol Burstein (WE), August 26, 1981, regarding routine inspection conducted on July 1-31, 1981, of activities at Point Beach Nuclear Power Plant, Units 1 and 2.

45. Sol Burstein (WE) letter to H. R. Denton (NRC), August 28, 1981,

" Technical Specification Change Request No. 68, Containment Purge Valve Operability"

46. Sol Burstein (WE) letter to H. R. Denton (NRC), September 11, 1981,

" Modification of Instrument Power Supply"

47. Sol Burstein (WE) letter to H. R. Denton (NRC), September 14, 1981,

" Response to NUREG-0737, Update to Schedule Requirements and Implementa-tion Status"

48. R. A. Clark (NRC) letter to Sol Burstein (WE), September 14, 1981, regarding acceptance of item II.E.4.1, Dedicated Hydrogen Penetrations in NUREG-0737.

49. C. W. Fay (WE) letter to H. R. Denton (NRC) September 16, 1981, " Additional Information, Auxiliary Feedwater System"

50. D. G. Eisenhut (NRC) to All Licensees of Operating Plants and Applicants for Operating Licenses and Holders of Construction Permits, September 29, 1981, " Revised Schedule for Completion of TMI Action Plan Item II.D.1, Relief and Safety Valve Testing (Generic Letter No. 81-36).

50a. T. G. Colburn (NRC) letter to S. Burstein (WE), September 30, 1981,

" Issuance of Amendments 55 and 60 to PBNP."

51. T. G. Colburn (NRC) letter to Wisconsin Electric Power Company, October 7, 1981, " Summary of Meeting Held with Licensee tn Discuss Integrated Scheduling of NUREG-0737 Items with Other NRC Requirements"

52. C. W. Fay (WE) letter to H. R. Denton (NRC), October 20, 1981, " Reactor Vessel Water Level Indication System Description"

53. R. W. Jurgensen (WOG) letter to D. G. Eisenhut (NRC), OG-64, November 30,

) 1981, " Emergency Response Guideline Program" i 54. R. A. Clark (NRC) letter to Sol Burstein (WE), December 2,1981, "TMI I Action Plan Items I.A.1.3, I.C.5, and I.C.6 as Described in NUREG-0737"

55. C. W. Fay (WE) letter to H. R. Denton (NRC), December 16, 1981, " Prompt Notification System"

56. C. W. Fay (WE) letter to H. R. Denton (NRC), December 29, 1981, " Functional Description and Proposed Implementation Schedule - Meteorological l Monitoring System" l

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Revision 4 July 9, 1984

57. C. W. Fay (WE) letter to H. R. Denton (NRC) December 29, 1981, "NUREG-0737 i Items II.F.1.1 and II.F.1.2"

58. O. D. Kingsley (WOG) letter to H. R. Denton (NRC), OG-66, December 30, 1981, " Reactor Vessel Integrity"

59. R. A. Clark (NRC) letter to Sol Burstein (WE), January 13, 1982, "NUREG-0737 Item I.A.1.1 Shift Technical Advisor (STA)"

60. D. G. Eisenhut (NRC) letter To All Licensees of Operating Plants, Applicants for an Operating License, and Holders of Construction Permits, February 8,1982, " Nuclear Power Plant Staff Working Hours (Generic Letter No. 82-02)"

61. R. A. Clark (NRC) letter to C. W. Fay (WE) February 11, 1982, " Status of NUREG-0737 Item II.F.3 (sic) for Point Beach Nuclear Plant Units 1 and 2"

62. C. W. Fay (WE) letter to J. G. Keppler (NRC), February 18, 1982,

" Minimum Staffing Requirements for NRC Licensees for Nuclear Power Plant Emergencies (Table III. A.1.2-1 or Table B-1 of NUREG-0654, Revision 1) and Point Beach Nuclear Plant Conformance"

63. R. A. Clark (NRC) letter to C. W. Fay (WE) February 18, 1982, "NUREG-0737 Item III.D.S.3., Improved In-Plant Iodine Instrumentation Under Accident Condition"

64. H. B. Clayton (NRC) memorandum for D. L. Ziemann (NRC), February 24, 1982, " Meeting Summary, Westinghouse Owners' Group and Westinghouse Emergency Operating Procedure Guidelines"

65. R. A. Clark (NRC) letter to C. W. Fay (WE) February 25, 1982, " Status of NUREG-0737 Items II.F.1.1 and II.F.1.2 for Point Beach Nuclear Plant, Units 1 and 2"

66. C. W. Fay (WE) letter to J. G. Keppler (NRC), March 8, 1982, " Minimum Staffing Requirements for NRC Licensees for Nuclear Power Plant Emergencies (Table III.A.1.2-1 or Table B-1 of NUREG-0654, Revision 1) and Point Beach Nuclear Plsnt Conformance"

67. C. W. Fay (WE) letter to H. R. Denton (NRC), March 16,1982, " Auxiliary Feedwater Automatic Initiation"

68. D. G. Eisenhut (NRC) letter To All Licensees of Operating Power Reactors, March 17, 1982, " Post-TMI Requirements (Generic Letter No. 82-05)"

69. R. A. Clark (NRC) letter to C. W. Fay (WE), March 24, 1982, "TMI Action Plan Item II.K.3.3, Reporting Relief Valve (RV) and Safety Valve (SV) Failures and Challenges"

Revision 4 July 9, 1984 69a. E. P. Rahe (W) letter to D. G. Eisenhut (NRC), NS-EPR-2581, March 26, 1982, " Westinghouse Small Break ECCS Evaluatin Model."

70. J. G. Keppler (NRC) letter to Sol Burstein (WE), March 31, 1982, regarding minimum onsite emergency staffing.

71. C. W. Fay (WE) letter to H. R. Denton (NRC), April 8, 1982, "Further Response to NUREG-0737, Item II.D.1"

72. R. L. Spessard (NRC) letter to S. Burstein (WE), April 8, 1982, "Installa-tion Deficiencies in Conduit Installed as a Part of TMI Modification Program."

73. P.S. Kappo (NRC) memorandum for W. R. Butler (NRC), April 12, 1982, "NUREG-0737 Item II.F.1.4, Containment Pressure Monitor System (CPMS):

Method for Estimating the Combined Time Constant of a String of Compon-ents each of which has a Known Time Constant."

74. S. Burstein (WE) letter to H. R. Denton (NRC), April 20, 1982, " Response j to Generic Letter No. 82-05, Post-THI Requirements."

74a. R. A. Clark (NRC) letter to C. W. Fay (WE), April 21, 1982, " Item II.E.1.1, AFW System Evaluation for P8NP, Units 1 and 2.

75. C. W. Fay (WE) letter to H. R. Denton (NRC), April 26, 1962, " Response to NUREG-0737, Update to Schedule Requirements and Implementation Status."

76. R. A. Clark (NRC) letter to C. W. Fay (WE), May 3, 1982, "NUREG-0737 Item II.E.1.2 Auxiliary Feedwater System Automatic Initiation and Flow Indication." -

77. C. W. Fay (WE) letter to H. R. Denton (NRC), May 4, 1982, " Additional Response to NRC Generic Letter No. 81-14."

78. D. G. Eisenhut (NRC) letter to All Licensees of Operating Power Reactors, May 5, 1982, " Post-TMI Requirements", (Generic Letter No. 82-10).

79. C. W. Fay (WE) letter to D. G. Eisenhut (NRC), May 19, 1982, " Shift and Licensed Operator Staffing."

' 80. C. W. Fay (WE) letter to J. G. Keppler (NRC), May 19, 1982, " Staffing Levels for Emergency Situations Point Beach Nuclear Plant."

81. L. 8eltracchi and G. Lapinsky (NRC) memorandum for V. A. Moore (NRC),

May 19, 1982, "SAS Demonstration."

82. S. Burstein (WE) letter to R. M. Eckert (PSE&G), June 2,1982, "S.B.

Comment on his Views Regarding Shift Staffing."

83. D. G. Eisenhut (NRC) letter to All Licensees of Operating Plants, Applicants for an Operating License and Holders of Construction Permits, June 15, 1982, " Nuclear Plant Staff Working Hours" (Generic Letter No. 82-12).

_ _ _ _ . -~ - - -

Revision 4 July 9, 1984 I

84. D. G. Eisenhut (NRC) letter to All Power Reactor Licensees Applicants j for an Operating License and Holders of a Construction Permit, June 17, 1982, " Reactor Operator and Senior Reactor Operator Examinations" (Generic Letter No. 82-13).

84a. C. W. Fay (WE) letter to H. R. Denton (NRC), June 18, 1982, " Reactor Cool-ant System Gqs Vent System."

85. J. A. Calvo (NRC) memorandum for H. R. Denton et al. (NRC), June 25, 1982, " Daily Highlight: Suspension of Completion Schedules for Environ-mental Qualification of Safety Related Electrical Equipment."

86. R. A. Clark (NRC) letter to C. W. Fay (WE), June 30, 1982, "HUREG 0737 Item II.8.3, Post-Accident Sampling System."

87. C. W. Fay (WE) letter to H. R. Denton (NRC), June 30,1982, "Further Response to NUREG-0737 Item II.D.1 Relief and Safety Valve Testing."

88. S. Burstein (WE) letter to H. R. Denton (NRC), July 15, 1982, " Emergency Support Center."

89. C. W. Fay (WE) letter to H. R. Denton (NRC), July 20, 1982, " Additional Information Concerning NUREG-0737 Implementation Schedules."

90. B. King (WOG) letter to R. A. Newton (WE), August 5, 1982, "NUREG-0737, Item II.K.3.30 New Small Break LOCA Model."

91. E. P. Rahe (WEC) letter to D. G. Eisenhut (NRC), June 28, 1982, " Supplemental Information of New Small Break LOCA Model to Address NUREG-0737 Item II.K.3.30."

92. C. W. Fay (WE) letter to H. R. Denton (NRC), August 9, 1982, "Further Response to NUREG-0737, Item II.D.1."

93. R. A. Clark (NRC) letter to C. W. Fay (WE), August 10, 1982, "NUREG-0737 Item III.D.3.4 Control Room Habitability at Point Beach Nuclear Plant"

(

Attachment:

PNL letter dated March 2, 1982).

94. T. G. Colburn (NRC) letter to C. W. Fay'(WE), August 11, 1982, " Acknowledges receipt of our July 15, 1982 letter regarding the EOF for P8NP."

95. P. S. Kappo (NRC) memorandum for W. R. Butler (NRC), August 23, 1982, "NUREG-0737, Analytical Solutions to Two Problems Pertinent to Items II.F.1.4, 5, 6."

96. S. Surstein (WE) letter to D. G. Eisenhut (NRC), August 28, 1982, " Operator Licensing."

97. D. G. Eisenhut (NRC) letter to All Pressurized Power Reactor Licensees.

September 20, 1982, "NUREG-0737 Technical Specifications" (Generic Letter No. 82-16). -

1

Revision 4 July 9, 1984

98. C. W. Fay (WE) to H. R. Denton (NRC), September 24, 1982, " Additional Information NUREG-0737 Item II.B.2, Plant Shielding."

99. C. W. Fay (WE) letter to USNRC Attention: S. J. Chilk (NRC), September 27, 1982, " Proposed Rule 10 CFR 50 Licensed Operator Staffing .t Nuclear Power Plants."

100. C. W. Fay (WE) letter to H. R. Denton (NRC), September 29, 1982, " Reschedule of Error Analysis Reactor Vessel Water Level Instrumentattion System."

101. C. W. Fay (WE) letter to H. R. Denton (NRC), September 30, 1982, " Emergency Support Center."

102. D. P. Hoffman (Consumers Power Company) letter to H. R. Denton (NRC),

September 30, 1982, " Transmittal of PWR Safety and Reitef Valve Test Program Reports."

103. S. Burstein (WE) letter to H. R. Denton (NRC), September 30, 1982, "NUREG-0737 Item II.B.3 Post-Accident Sampling System."

104. R. A. Clark (NRC) letter to C. W. Fay (WE), October 8,1982, "Regarding a Design Deficiency in ESF Reset Controls for Steam Generator Blowdown Line 4

Isolation Valves."

105. C. W. Fay (WE) letter to H. R. Denton (NRC), October 15, 1982, " Reactor Coolant System Gas Vent System."

j 106. R. A. Clark (NRC) letter to C. W. Fay (WE), October 19. 1982, " Request for Additional Information - TMI Item II.K.3.25, Power to Pump Seals."

107. S. Burstein (WE) letter to H. R. Denton (NRC), November 9,1982, " Response to Request for Additional Information Locked Rotor and LOCA Analyses."

108. R. A. Clark (NRC) letter to C. W. Fay (WE), November 15, 1982, "NUREG-0737 TMI Action Plan Items I.A.2.1, ' Upgrading RO and SRO Training' and II.B.4, ' Training for Mitigating Core Damage'."

109. D. G. Eisenhut (NRC) letter to 0. D. Kingsley (WOG), November 18, 1982,

" Regulatory Guide 1.97, Rev. 2 Requirements for Reactor Coolant Temper-ature Indication."

110. D. G. Eisenhut letter to All Licensees of Operating Westinghouse and CE PWRs (Except Arkansas Nuclear One - Unit 2 and San Onofre Units 2 and 3),

December 10, 1982, " Inadequate Core Cooling Instrumentation System" (Generic Letter No. 82-28).

111. C. W. Fay (WE) letter to H. R. Denton (NRC) September 15, 1982, " Seismic Qualification of the Auxiliary Feedwater System."

111a. Westinghouse letter to NRC, NSEPR-2681, November 12, 1982, WCAP 10079, "NOTRUMP: A Nodal Transient Small Break and General Network Code."

Revision 4 July 9, 1984 112. J. G. Keppler (NRC) letter to S. Burstein (WE), December 16, 1982, "TSC and EOF Voice Communications Equipment."

113. C. W. Fay (WE) letter to H. R. Denton (NRC), December 17, 1982, " Reactor ,

Coolant System Gas Vent System."

114. D. G. Eisenhut (NRC) letter to All Licensees of Operating Reactors, Aoplicants for Operating Licenses, and Holders of Construction Permits, December 17, 1982, " Supplement 1 to NUREG-0737 - Requirements for Emergency Response Capability" (Generic Letter No. 82-33).

115. E. L. Jordan (NRC) information notice to All holders of a nuclear power reactor operating license (OL) or construction permit (CP), December 20, 1982, " Modification of Solid State AC Undervoltage Relays Type ITE-27" (IE Information Notice No. 82-50).

116. R. A. Clark (NRC) letter to C. W. Fay (WE), December 22, 1982, " Safety Evaluation Report (SER) on NUREG-0737 Item II.B.3 Post-Accident Sampling System at PBNP."

116a. Westinghouse letter to NRC, NSEPR-2694, December 22, 1982, WCAP 10054,

" Westinghouse Small Break ECCS Evaluation Model Using The NOTRUMP Code."

117. C. W. Fay (WE) letter to H. R. Denton (NRC) December 23, 1982, "Further Response to NUREG-0737, Item II.D.1 Relief and Safety Valve Testing."

118. D. G. Eisenhut (NRC) letter to All Licensees and Applicants for Operating Power Reactors and Holders of Construction Permits for Power Reactors, December 28, 1982, " Filings Relating to 10 CFR 50 Production and Utilization Facilities" (Generic Letter No. 82-30).

119. C. W. Fay (WE) letter to H. R. Denton (NRC), December 28, 1982, " Request for Additional Information TMI Item II.K.3.25, Power to Pump Seals."

120. C. W. Fay (WE) letter to H. R. Denton (NRC), January 19, 1983, "Instru-mentation Error Analysis Reactor Vessel Water Level Indication System."

121. R. A. Clark (NRC) letter to C. W. Fay (WE), January 25, 1983, " Exemption from the Schedular Requirements of Paragraph (c)(3)(iii) of 10 CFR 50.44."

122. E. L. Jordan (NRC) information notice to All nuclear power reactor facilities holding an operating license (0L) or construction permit (CP),

January 28, 1983, " Calibration of Liquid Level Instruments (Information Notice 83-03).

123. R. A. Clark (NRC) letter to C. W. Fay (WE), February 2,1983, " Request for Additional Information on NUREG-0737 Items: II.F.1.4, Containment Pressure Monitor; II.F.1.5, Containment Water Level Monitor; II.F.1.6, Containment Hydrogen Monitor."

l

i i

Revision 4 July 9, 1984 124. R. A. Clark (NRC) letter to C. W. Fay (WE), Febraury 4, 1983, "NUREG-0737 '

Item II.K.3.25, Loss of AC Power to Reactor Coolant Pump Seals."

125. D. G. Eisenhut (NRC) letter to All Operating Reactor Licensees, February 8, 1983, " Licensee Qualification for Performing Safety Analyses in Support of Licensing Actions" (Generic Letter No. 83-11).

126. D. G. Eisenhut (NRC) letter to All Licensees with Westinghouse (W)

Designed Nuclear Steam Supply Systems (NSSSs) (Except Yankee Atomic Electric Company), February 8,1983, " Resolution of TMI Action Item II.K.3.5, ' Automatic Trip of Reactor Coolant Pumps'" (Generic Letter No.83-10d).

127. C. W. Fay (WE) letter to H. R. Denton (NRC), February 11, 1983, " Auxiliary Feedwater System Modifications."

128. R. A. Muench (WOG) letter to Technical Specification Subcommittee Members WOG-83-120, February 15, 1983, "NUREG-0737 Items Requiring Implementation

• Into Plant Technical Specifications" (Attachment is the below letter).

129. D. G. Eisenhut (NRC) letter to 0. D. Kingsley (WOG), January 28, 1983, NUREG-0737 Items Requiring Technical Specifications" (Attachment is DRAFT Generic Letter for Comment on NUREG-0737 Technical Specifications).

130. C. J. Paperiello (NRC) letter to S. Burstein (WE), Febraury 16, 1983,

" Routine Safety Inspection of P8NP on January 25-27, 1983."

131. C. W. Fay (WE) letter to H. R. Denton (NRC), February 21, 1983, "NUREG-0737 Item II.B.3, Post-Accident Sampling System."

132. E. L. Jordan (NRC) memorandum for D. G. Eisenhut (NRC), February 24, 1983, " Response to Request for Technical Assistance (Review of Licensee's (WE) Provisions for On-Shift Staffing)."

133. C. W. Fay (WE) letter to H. R. Denton (NRC), February 28, 1983, " Reply to NRC Request for Additional Information on NUREG-0737, Items II.F.1.4, II.F.1.5, and II.F.1.6."

134. D. G. Eisenhut (NRC) letter to All Licensees of Operating Reactors, Applicants for Operating Licensees, and Holders of Construction Permits, March 7,1983, " Definition of Key Maintenance Personnel", (Clarification of Generic Letter 82-12) (Generic Letter No. 83-14).

135. C. W. Giesler (Wisconsin Pubitc Service Corporation) letter to D. G. Eisenhut  !

(NRC), March 9, 1983, " Inadequate Core Cooling (ICC) Instrumentation System."

135a. J. J. Sheppard (WOG) letter to D.G. Eisenhut (NRC), March 14, 1983, OG-91, "RCS integrity Function Restoration Guidelines for the High-Pressure and Low Pressure Versions of the Emergency Response Guidelines Set."

136. R. A. Clark (NRC) letter to C. W. Fay (WE), March 14, 1983, " Confirming Order on Items Set Forth in NUREG-0737."

Revision 4 July 9, 1984 137. C. W. Fay (WE) letter to H. R. Denton (NRC), March 21, 1983, " Reply to Generic Letter No. 82-28.

138. C. W. Fay (WE) letter to H. R. Denton (NRC), March 24, 1983, " Auxiliary Feedwater System Operability."

139. R. A. Muench (WOG) letter to WOG Representatives, WOG-83-150, March 30, 1983, " Potential for Voiding in the RCS During Transients - NUREG-0737, Item II.K.2.17" (Attached letter is below).

140. R. A. Muench (WOG) letter to D. G. Eisenhut (NRC), NSID/WOG-63, February 16, 1983, " Potential for Voiding in the Reactor Coolant System during Transients NUREG-0737 - Item II.K.2.17."

141. R. A. Muench (WOG) letter to WOG Representatives and Analysis Subcom-mittee Members, WOG-83-151, March 31, 1983, "WOG Generic Response to NRC Letters83-10c & d."

142. C. W. Fay (WE) letter to H. R. Denton (NRC), April 5, 1983, " Reactor Coolant System Gas Vent System."

143. C. W. Fay (WE) letter to H. R. Denton (NRC), April 11, 1983, " Response to Generic Letter No.83-10d."

143a. J. J. Sheppard (WOG) letter to D. G. Eisenhut (NRC), April 13, 1983, OG-98,

" Low-Pressure Version of the Emergency Response Guidelines."

144. C. W. Fay (WE) letter to H. R. Denton (NRC), April 15, 1983, " Response to Generic Letter 82-33 Update to Senedule Requirements for Emergency Rssponse Capability."

144a. Technical Evaluation Report on the WOG report in response to NUREG-0737 Item II.K.3.2, dated February 15, 1903, revised April 21, 1983.

145. W. J. Johnson (W) letter to D. K. Porter (WE), WEP-83-545, May 5,1983,

" Elimination of Postulated RCS Primary Loop Pipe Breaks" 146. C. W. Fay (WE) letter to H. R. Denton (NRC), May 6,1983, " Implementation of THI-Related Issues."

147. D. G. Eisenhut (NRC) letter to All Operating Reactor Licensees and Holders of Construction Permits, May 9, 1983, " Integrated Scheduling for Implementation of Plant Modifications" (Generic Letter 83-20).

148. R. A. Clark (NRC) letter to C. W. Fay (WE), May 9, 1983, " Exemption from Schedular Requirements of 10 CFR 50.44(c)(3)(iii), Reactor Coolant System (RCS) High Point Gas Vents for Unit 2."

149. R. A. Clark (NRC) letter to C. W. Fay (WE), May 12, 1983, "NUREG-0737 Item III.A.2.1 Emergency Plan Upgrade to Meet Rule."

I l

Revision 4 July 9, 1984 150. Preliminary Notification of Event or Unusual Occurrence--PNO-111-83-37, PBNP Units 1 and 2, May 18, 1983, " Noble Gas Effluent Monitor Not Installed as Required."

150a. C. W. Fay (WE) letter to H. R. Denton (NRC), May 20, 1983, " Environmental Qualification of Eiectrical Equipment Important to Safety within the Scope of 10 CFR 50.49."

151. C. W. Fay (WE) letter to S. J. Chilk (NRC), May 20, 1983, " Emergency Operations Facility Location."

152. J. G. Keppler (NRC) letter to S. Burstein (WE), May 20, 1983, " Confirms our Commitment to have Noble Gas Effluent Monitors Installed and Operating by June 30, 1983."

153. C. W. Fay (WE) letter to H. R. Denton (NRC), May 25, 1983, " Additional Information NUREG-0737."

154. D. G. Eisenhut (NRC) letter to All Operating Reactor Licensees, Applicants for an Operating License and Holders of Construction Permits for Westing-house Pressurized Water Reactors, June 3,1983, " Safety Evaluation of

' Emergency Response Guidelines'" (Generic Letter 83-22) (Attachment is letter below).

155. D. G. Eisenhut (NRC) letter to J. J. Sheppard (WOG), June 1, 1983,

" Safety Evaulation of ' Emergency Response Guidelines'."

156. C. W. Fay (WE) letter to H. R .Denton (NRC), June 3, 1983, " Chemical Test Matrix."

157. R. C. DeYoung (NRC) letter to C. W. Fay (WE), June 3, 1983, " Response to our Request to Locate a Portion of the EOF in Milwaukee."

158. J. A. Hind (NRC) letter to S. Burstein (WE), June 10, 1983, " Commission's Review of On-Shift Staffing and Augmentation for Emergency Situations at PBNP."

159. R. A. Muench (WOG) letter to D. G. Eisenhut (NRC), June 14, 1983, " Regulatory Guide 1.97, Rev. 2, Requirements for Reactor Coolant Temperature Indication" (Attachment is a revised letter OG-94 (Revised) dated June 14,1983).

160. J. J. Sheppard (WOG) letter to D. G. Eisenhut (NRC), June 14, 1983, OG-94 (Revised), " Regulatory Guide 1.97, Rev. 2, Requirements for Reactor Coolant Temperature Indication."

161. R. A. Newton memorandum to J. J. Zach, June 16, 1983, " Additional Inputs to the Backup Computer."

162. C. W. Fay (WE) letter to H. R. Denton (NRC), June 16, 1983, "Implementa-tion of Post TMI-Related Issues."

_. _.._ ~ _ _ _ _ . . _ . - _ _ _- - - _ __ _ _ - - , _ . .

b

^

Revision 4 July 9, 1984 a 163. C. W. Fay (WE) letter to R. C. DeYoung (NRC), June 16, 1983, " Location of j Emergency Operations Facility."

i 164. C. W. Fay (WE) letter to H. R. Denton (NRC), June 20, 1983, " Auxiliary Feedwater System Operability."

165. R. A. Clark (NRC) letter to C. W. Fay (WE), June 21, 1983, "NUREG-0737

Items II.F.1.4 Containment Pressure Monitor System, II.F.1.5 Containment i Water Level Monitor System, II.F.1.6 Containment Hydrogen Monitor System '

for P8NP Units 1 and 2."

l 166. S. Burstein (WE) letter to H. R. Denton (NRC), June 22, 1983, " Request for l

Extension of Deadline for Certain Environmental Qualification Items."

! 167. C. W. Fay (WE) letter to H. R. Denton (NRC), June 29, 1983, " Installation of SA-11 Monitors" i 168. C. W. Fay (WE) letter to H. R. Denton (NRC), June 30, 1983, " Electric

Power Distribution System."

! 169. C. J. Paperiello (NRC) letter to S. Burstein (NRC), July 1,1983, " Refers to Special Safety Inspection Conducted by P. C. Lovendal (NRC)."

j 170. R. A. Clark (NRC) letter to C. W. Fay (WE), July 12, 1983, " Response to our Request for Modification of NRC Confirming Order of March 14, 1983."

f 171. C. W. Fay (WE) letter to H. R. Denton (NRC), July 12, 1983, " Containment

Atmosphere Sampling."

l

! 172. C. W. Fay (WE) letter to J. G. Keppler (NRC), July 27, 1983, " Response to l NRC Inspection Report Nos. 50-266/83-08 and 50-301/83-08."

i

_ 173. C. W. Fay (WE) letter to H. R. Denton (NRC), July 27, 1983, " Reactor i

Cavity Annulus Seal Ring."

174. R. A. Clark (NRC) letter to C. W. Fay (WE), August 9, 1983, " Review of 1

TMI Item II.K.3.17 Report on Outages of ECC Systems."

I

! 175. C. W. Fay (WE) letter to H. R. Denton (NRC), August 24, 1983, " Supplemental Response to Generic Letter 82-33 Schedule Requirements for Emergency Response Capabilities."

l 176.. C. W. Fay (WE) letter to H. R. Denton (NRC), September 1, 1983, "Implementa-l tion of Regulatory Guide 1.97 for Emergency Response Capability."

l I 176a. Background Information for WOG Emergency Response Guidelines, Generic Issue, l Reactor Vessel Liquid Inventory System, September 1, 1983.

177. J. A. Hind (NRC) letter to S. Burstein (WE), September 12, 1983, " Inspection Report 83-14."

Revision 4 July 9, 1984 4

178. D. G. Eisenhut (NRC) letter to S. Burstein (WE), September 14, 1983,

" Refusal to Move Emergency Support Center to Milwaukee."

179. J. R. Miller (NRC) letter to C. W. Fay (WE), September 15, 1983, "Modifica-tions to Motor-Drive AFW Pump Isolation Valves."

180. J. R. Miller (NRC) letter to C. W. Fay (WE), September 16, 1993, "NUREG-0737 Items II.K.3.1-Automatic PORV Isolation and II.K.3.2-Report on PORV's for P8NP."

181. J. R. Miller (NRC) letter to C. W. Fay (WE), September 22, 1903, "NUREG-0737 Item II.B.1, Reactor Coolant System Vents."

t 181a. J. J. Sheppard (WOG) letter to D. G.Eisenhut (NRC) OG-105, September 27, 1983, " Response to Safety Evaluation of the Westinghouse Owners Group Emergency Response Guidelines."

182. C. W. Fay (WE) letter to H. R. Denton (NRC), September 30, 1983, " Rule 10 CFR 50 Licensed Operator Staffing at Nuclear Power Plants."

182a. S. Burstein (WE) letter to NRC Commissioners, October 6,1983, " Accident Source Term."

183. C. W. Fay (WE) letter to H. R. Denton (NRC), October 10, 1983, " Resolution of Safety Evaluation Reports for Environmental Qualification of Safety-Related Electrical Equipment."

184. C. W. Fay (WE) letter to H. R. Denton (NRC) October 10, 1983, " Modification of Implementation of NUREG-0578 (DTA)."

185. J. R. Miller (NRC) letter to C. W. Fay (WE), October 12, 1983, "NUREG-0737 Item II.B.1 Reactor Coolant System Vents."

186. S. Burstein (WE) letter to D. G. Eisenhut (NRC), October 14, 1983,

" Emergency Support Center."

186a. J. J. Sheppard (WOG) letter to D. Crutchfield (NRC), October 31, 1983,

" Emergency Response Guidelines, Rev.1, Validation Program."

187. D. G. Eisenhut (NRC) letter to All PWR Licensees, November 1, 1983, "NUREG-0737 Technical Specifications (Generic Letter 83-37)."

188. D. G. Eisenhut (NRC) letter to All Licensees, November 2, 1983, " Clarification i

of TMI Action Plan Item II.K.3.31 (Generic Letter No. 83-35)."

! 189. J. R. Miller (NRC) letter to C. W. Fay (WE), November 3, 1983, " Post Accident Sampling System (NUREG-0737 Item II.B.3)."

190. J. R. Miller (NRC) letter to C. W. Fay (WE) November 3,1983, "NUREG-0737 Item I1.8.2.2 Plant Shielding Modifications for Vital Area Access."

l

Revision 4 July 9, 1984 190a. C. W. Fay (WE) letter to J. G. Keppler (NRC), November 7, 1983, " Response to NRC Inspection Report No. 50-301/83-11."

191. J. R. Miller (NRC) letter to C. W. Fay (WE), Nove:nber 8,1983, " Review of Natural Circulation Cooldown (Genreic Letter No. 81-21)."

192. R. B. Minogue (NRC) memorandum to R. F. Fraley (ACRS), November 10, 1983,

" Revision 1 to Reg. Guide 1.89, ' Environmental Qualification of Electric Equipment Important to Safety for Nuclear Power Plants.'"

193. C. W. Fay (WE) letter to H. R. Denton (NRC), November 11, 1983, "Autiliary Feedwater System Operability."

194. C. W. Fay (WE) letter to H. R. Denton (NRC), November 18, 1983, "Emargency Operations Facility."

195. C. W. Fay (WE) letter to H. R. Denton (NRC), November 23, 1983, " Resolution of Safety Evaluation Reports for Environmental Qualification of Safety-Related Equipment."

196. C. W. Fay (WE) letter to H. R. Denton (NRC), November 29, 1983, " Reactor Coolant System High Point Gas Vents."

196a. J. J. Sheppard (WOG) letter to R. J. Mattson (NRC), December 1, 1983,

, OG-110, ",WOG Report on Evaluation of Alternate RCP Trip Criteria."

197. C. W. Fay (WE) letter to H. R. Denton (NRC), December 6, 1983, " Core Damage Assessment Methodology, NUREG-0737 Item II.B.3."

198. T. G. Colburn (NRC) letter to C. W. Fay, December 28, 1983, " Amendments 79 and 84 to Units 1 and 2, respectively."

199. C. W. Fay (WE) letter to H. R. Denton (NRC), December 29, 1983, "Further Response to Generic Letter No.83-10d, Automatic Trip of Reactor Coolant Pump."

200. J. R. Miller (NRC) letter to C. W. Fay (WE), December 29, 1983, " Issuance of Amendment Nos. 80 and 85 to PBNP Units 1 and 2" (AFW System testing).

201. J. R. Miller (NRC) letter to C. W. Fay (WE), December 30, 1983, " Shift Manning Rule."

202. J. R. Miller (NRC) letter to C. W. Fay (WE), December 30, 1983, " Exemption from Schedular Requirements of Paragraph (c)(iii) of 10 CFR 50.44 for Installation of Reactor Coolant System High Point Gas Vents."

l 203. H. R. Denton (NRC) letter to S. Burstein (WE.), January 3,1984, " Extension of Deadline Established in 10 CFR 50.49 for Final Environmental Qualification of Certain Safety Related Eler.trical Equipment."

204. C. W. Fay (WE) letter to J. G. Keppler (NRC), January 4,1984, " Final  !

Response to I. E. Bulletin 79-14." '

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Revision 4 July 9, 1984 205. J. R. Miller (NRC) letter to C. W. Fay (WE), January 24, 1984, "NUREG-0737 Item II.K.2.17, Potential for Voiding in the Reactor Coolant System During Transients."

206. T. G. Colburn (NRC) memorandum to J. R. Miller (NRC), January 24, 1984,

" Meeting Summary Re: WEPC0 Shift Staffing Exemption Request for PBNP, Units 1 and 2."

207. C. W. Fay (WE) letter to H. R. Denton (NRC), January 31, 1984, " Auxiliary Feedwater System Modifications."

208. C. J. Paperiello (NRC) letter to S. Burstein (WE), February 2, 1984,

" Safety Evaluation Report on the P8NP Emergency Plan," Report Nos. 50-266/

83-25; 50-301/83-23.

209. C. W. Fay (WE) letter to H. R. Denton (NRC), February 14, 1984, " Rule 10 CFR 50 Licensed Operator Staffing."

210. W. D. Shafer (NRC) letter to S. Burstein (WE), February 22, 1984, "Inspec-tion Report No. 266/83-26; No. 301/83-24."

211. C. W. Fay (WE) letter to H. R. Denton (NRC), February 29, 1984, "Specifica-tions for TMI Backfit Instrumentation Technical Specifications Change Re-quest No. 96."

212. J. J. Sheppard (_WOG) letter to J. Norris (NRC), February 29, 1984, OG-116, "NUREG-0737, Item II.B.3 Post Accident Core Damage Assessment Methodology."

213. C. W. Fay (WE) letter to H. R. Denton (NRC), March 5, 1984, " Implementation of Post-TMI Related Issues."

214. C. W. Fay (WE) letter to J. G. Keppler (NRC), March 6,1984, " Inspection Report Nos. 50-266/83-25 and 50-301/83-23 Revised Emergency Plan Safety Evaluation Report.

215. C. W. Fay (WE) letter to H. R. Denton (NRC), March 8, 1984, " Additional Information on Generic Letter 82-33 Schedule Requirements for Emergency j Response Capabilities."

i 216. J. J. Sheppard ()f0G) letter to R. J. Mattson (NRC), March 9, 1984, OG-117

"_WOG Report on Justification of Manual RCP Trip for SBLOCA Events."

217. J. R. Miller (NRC) letter to C. W. Fay (WE), March 15, 1984, " Resolution  !

of the Issue of Upper Plenum Injection." l 218. C. W. Fay (WE) letter to H. R. Denton (NRC), March 19, 1984, " Technical Specification to Limit Overtime."

219. J. J. Sheppard ()f0G) letter to J. Norris (NRC), March 23, 1984, OG-118 "NUREG-0737, Item II.B.3 Post Accident Core Damage Assessment Methodology, Revision 1."

Revision 4 July 9, 1984 220. H. R. Denton (NRC) letter to C. W. Fay (WE), March 26, 1984, " Extension Request for Implementation of 10 CFR 50.54 (m)(2)(i)."

i 221. C. W. Fay (WE) letter to H. R. Denton (NRC), March 30, 1984, " Upgraded Emergency Operating Procedures."

222. C. W. Fay (WE) letter to H. R. Denton (NRC), April 10, 1984, " Reactor Cavity Annulus Seal Ring."

223. C. W. Fay (WE) letter to H. R. Denton (NRC), May 1, 1984, " Final Response to Generic Letter No.83-10d Automatic Trip of Reactor Coolant Pump."

224. T. A. Lordi (WOG) letter to Core Damage Assessment Working Group Members, WOG-84-172, May 2, 1984, "WOG Post-Accident Core Damage Assessment Methodology NUREG-0737, Item II.B.3 NRC Safety Evaluation Report."

225. C. W. Fay (WE) letter to H. R. Denton (NRC), May 3, 1984, " Additional Information on Generic Letter 82-33 Schedule Requirements for Control Room Design Review."

226. C. W. Fay (WE) letter to H. R. Denton (NRC), May 17, 1984, " Final Response to NUREG-0737 Item II.D.1 Relief and Safety Valve Testing."

i 227. C. W. Fay (WE) letter to H. R. Denton (NRC), June 1, 1984, " Procedures Generation Package Upgraded Emergency Operating Procedures."

228. J. R. Miller (NRC) letter to C. W. Fay (WE), June 6, 1984, "NUREG-0737, II.K.2.13, 'Thermo-Mechanical Report,' Point Beach Nuclear Plant."

229. C. W. Fay (WE) letter to H. R. Denton (NRC), June 26, 1984,

" Implementation of Post-THI Related Issues."

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UPDATE TO NUREG-0737 POST-TMI REQUIREMENTS e

FOR OPERATING PLANTS Point Beach Nuclear Plant Units 1 and 2 Docket Nos. 50-266 and 50-301 Schedule Table and Notes Revision 4 - July 9, 1984

l Key To Schedule Table N. A. = Schedule not applicable to Point Beach Nuclear Plant (P8NP)

N. R. = Not Required TBD = To Be determined at a later date per the remarks

• = Schedule is based on the timely delivery of equipment

+ = ASIP installation, startup, and testing complete by October 31, 1984 with new instruments integrated into procedures and operator training on procedures complete by January 31, 1985.

Marginal Revision Notation None = Original issue dated December 23, 1980 (Reference 12) 1 = Revision 1 dated March 31, 1981 (Reference 23) 2 = Revision 2 dated September 14, 1981 (Reference 47) 3 = Revision 3 dated April 26, 1982 (Reference 75) 4 = Revision 4 dated July 9, 1984 (Updated in this submittal)

Revisten 4 July 9, 1984 l I

1 1

1 I.A.1.3.1. Shift Mannina-Limit Overtime i i

i The initial requirements for this item were met in 1M1 and the item i I was closed by Mr. R. A. Clark's letter to WE dated December 2, 1981. However, l i subsequently the requirements were revised in NRC Generic Letters 42-02 and '

} 82-12 dated February 8 and June 15, 1982. The revised requirements, in part,  !

! stated that the overtime limits must be included in the technical specifica- l

tions. Rather than unnecessarily clutter our toch specs, we met the require-  !

monts for limiting overtime by making changes to our administrative procedures.  !

, As stated in our March 19, 1984 letter tc the MC, we feel that this item is  !

i not appropriate for the tech specs. Since we have incorporated the MC's guid-  !

I ance on staff overtime and working hours in our administrative procedures, T

and we are required by the. tech specs to operate the plant in accordance with  ;

approved procedures, we are in compliance with the requirements of this item. f We are currently awaiting MC approval of our proposal to delay a- l

! mending our operating license and revising our technical specifications in j

! anticipation of the. adoption of the Commission's proposed rule on te6hnical ,

{ specification content. This proposed rule, as published in 47 Federal Reefster i 13369, is an attempt to reduce the paperwork burden for both licensees and the }

! NRC staff due to the large number of proposed change requests that must be i processed.

i i

I.A.I.3.2 Shift Mannine-Minimum Shift Crew i

(  ;

4 As stated in Generic Letter 43-37 dated November 1, 1983 Item I.A.1.3  !

j has been superceded by rule 10 CFR 50.54(m), shift manning. Compliance with the  ;

i rule was originally required for January 1,1984. Reference 142 requested an  !

i extension of the requirement to Janaary 1, IM7 and requested two exemptions '

I to the rule. A meeting was held on January 10, 1984 to discuss our requests.  !

There, we agreed to drop the two exemption requests and to modify our request  :

for extension. By letter to the MC dated February 14, 1984, WE requested (

that an extension untti March 1, I M5 for compliance with the rule be granted.  !

3 Since this item is superceded by rule 10 CFR 50.54(m), we consider it to be '

j closed with respect to the TMI' Action Plan, t 1

!.C.1 Short-Ters Accident and_ Procedures Review I

The program to achieve compliance with NuttG-0737. Item I.C.1, was pre- t sented to the MC in a meeting held on June la,1981, and submitted to the MC by i Owners Group letter. 00-61, dated July 7, 1901, R. W. Jurgensen to 5. H. Nanauer i (Reference 36). The previous program submittal to the MC (Reference 20) resulted i j in several basic concerns which could not be easily resolved within the scope  !

of the material submitted. These MC concerns and the need to better or0anize I the set of emergency procedures resulted in a new configuration which was pre-

) sented to the MC at the June 14, 1981 meeting. The new procedure set, re-  ;

! ferred to as Emergency Response Guidelines (ERGS), was transmitted to the NRC  ;

{ by owners Group letter. 00-64, dated November 11, 1981 (Raference 53). Repre-l

) sentatives of the Westinghouse Owners Group met with the NRC en February 9, 1982 i

! to discuss the submitted ERes. A summary of the meeting is presented in Referorce ,

i 64.  !

l i

Revision 4 1 July 9, 1984 Additionally, the WOG has submitted descriptions of the ERG program in letters dated July 21, 1982 and January 4, 1983. The ERG program was re-viewed by the NRC. NRC Generic Letter 83-22 dated June 3, 1963 transmitted the Safety Evaluation of the ERG's and approved them for implenentation.

We are using Revision 1 of the ERG's to upgrade our Energency Ope -

ating Procedures. Revision 1 was issued to WOG members on Novemper 16, 1983.

Our letter of March 30, 1984 provided the current upgraded E0P implementation schedule. Our letter dated June 1,1984 provided the Procedures Generation Package for the development of the new E0P's. We expect final E0P implemen-tation to take place in January 1985.

I.D.1 Control Room Desion Review Our previous commitments for this item were covered in our first two responses to Supplement I to NUREG-0737 (Generic Letter 82-33 dated December 17, 1982). Those two letters were dated April 15 and August 24, 1983.

However, we recently revised our commitments in a letter to the NRC dated May 3, 1984. In that letter we stated that the program plan for the control room design review would be submitted to the NRC by July 31, 1984. The final report of the design review will be submitted in October 1985.

I.D 2 plant Safety Parameter Display Console Wisconsin Electric has undertaken two projects relating to the Safety Parameter Display System (SPOS). The first project was a joint effort with eleven other utilities and Quadrex Corporation to design and demonstrate a Safety Assessment System (SAS), our version of the SPOS. This demonstration SAS project was completed on May 20, 1982. In parallel with the SAS project, WE developed a specification for a new plant process computer system which would integrate the requirements of the SPOS, some af,pects of Regulatory Guide 1.97 instrumentation, and emergency response factitty plant data requirements.

The SAS was made part of the new plant process computer. In Septembe 1981 we signed a contract with Electronic Associates, Inc. (EAI) for a Safety Assessment System and Plant Process Computer System. In recordance with our March 8,1984 submittal on the current computer installation schedule, ve expect to have the SAS operational by December 31, 1985 ff the computer system is delivered in June of 1985.

!!.8.1 Reactor Coolant System Vents This item has been superseded by 10 CFR 50.44 (c)(?)(iii). NRC letter to Mr. C. W. Fay dated September 22, 1983 provided the Safetu Evaluation for our Reactor Coolant System Gas Vent System (RCS GVS) and closed thfs item from a NUREG 0737 standpoint.

The current status of our RCS GVS is as stated in our letter to the

• NRC dated November 29, 1983. The piping and valving for the RCS GVS have been installed and hydrostatically tested in both Point 8each units. Using interim power supplies and an Interim control panel, the RCS GVS may be remotely operated from the cable spreading room of the control butiding for both units, with the exception of the Unit 2 remote vent to containment. The valve for this vent path did not pass the leakage test; the valve was removed

. . ~ . . - -- - - - . _ - -

I

' Ravision 4

! July 9, 1984 and the line was capped. The valve was returned to the vendor for rework and testing. . It is scheduled to be replaced during the next Unit 2 refueling outage. scheduled for fall 1984. Final completion and full operation of the RCS GVS is also dependent upon delivery, installation, and startup of the Auxiliary Safety Instrumentation Panels (ASIPs) where the final controls will

, be located and the upgraded permanent power supplies as well as the upgrading i of Emergency Operating Procedures addressed by Item I.C.1. It is expected 1

that these items will be complete in December 1984. Also, the upgraded E0P's

which will address the RCS GVS will be implemented in January 1985. By letter dated December 30, 1983, the NRC granted an exemption from the schedule re-quirements of 10 CFR 50.44 (c)(3)(iii) until December 31, 1984.

II.B.2 Plant Shielding We have completed the requirements for item II.B.2-Plant Shielding.

Subitem II.B.2.2-Plant Shielding Modifications for Vital Area Access was closed by the NRC's Safety Evaluation dated November 3, 1983. Subitem II.B.2.3-Radia-tion Qualification of Safety-Related Equipment is also complete. Both items were listed as closed in Inspection Reports No. 266/83-26 and No. 301/83-24 dated February 22, 1984.

i II.B.3 Post Accident Sampling

i The final Safety Evaluation for the Point Beach Post Accident Sampling System (PASS), transmitted by letter dated November 3, 1983, stated that Item II.B.3 was considered complete for our plant and that any further action asso-ciated with the PASS would be handled on a plant specific basis.

The remaining action pertaining to this item is the incorporation of a revised core damage assessment methodology in our imergency Plan Imple-menting Procedures (EPIP's). This methodology was developed by Westinghouse for the Westinghouse Owner's Group (WOG) and was submitted to the NRC by letter OG-116 dated February 29, 1984. Revision 1 to the methodelogy was submitted by letter OG-118 dated March 23, 1984. The NRC SER dated April 10, 1984, provided the approval of Revision 1. We received-the SER via WOG letter WOG-84-172 dated May 2, 1984. We are using Revision 1 for our EPIP's.

4 Also, in Reference 103, we committed to environmentally qualify the electrical components for the instrument air containment isolation and residual heat removal sample valves to enhance post accident sampling capability. Unit 1 is complete and Unit 2 will be done by November 1,1984.

II.D.1.2 Relief and Safety Valve Test Requirements

, In Reference 117, we committed to implement several modifications to improve the' capability of piping rnd supports to accvamodate the calculated

( valve actuation loads during transient conditions. These modifications were ccepleted during the Spring 1983 refueling and steam generator sleeving outage

for Unit 2 and during the Fall 1983 refueling and steam generator replacement outage for Unit 1. The completion of these modifications fulfills the require-ments of this item. Our fi al response to this ites was dated May 17, 1984.

, The NRC's Confirmatory Letter of July 12, 1983 lists this item as complete.

Although we have received no safety evaluation, we consider this item closed.

~ - a: _ _ _ . _ _ _ _ . _ _ _ _ _ _ _ _ _ - _

Revision 4 July 9, 1984 i

II.D.1.3 Block Valve Testing Our letter to the NRC dated August 9, 1982 was our final submittal concerning block valve testing. In this letter we concluded that the EPRI/

Marshall Electric Motor Operated Valve (block valve) Interim Test Data Report dated May 31, 1982 fulfilled the NUREG-0737 requirements to provide test evidence to verify that block valves installed at Point Beach Nuclear Plant will function properly over the range of expected operating and accident conditions. The confirmatory letter from the NRC dated July 12, 1983 listed this item as complete.

II.D.3.1 Direct Indication of Relief and Safety Valve Position Adapters and Lift Indicating Switch Assemblies (LISA's) will be mounted on the pressurizer safety valves to provide direct indication of valve position. The assemblies have been purchased and received from Crosby for use on Crosby valves. These switch assemblies use magnetically operated reed switches to provide separately powered and redundant, open, midpoint and closed indications. These position indications will be provided for each of the 2 valves for each unit in the control room on the ASIPs.

The lift indicating switch assemblies are not presently qualified but Crosby is expected to qualify the assemblies. The reason the lift indicating switch assemblies will be installed is that they provide position indication based directly on valve position and are easier to environmentally qualify than the presently installed acoustic monitoring system. The presently installed acoustic monitoring system will continue to be used until the new assemblies are installed.

Paragraph (g) of NRC rule 10 CFR 50.49 imposed an environmental qual-ification deadline for this equipment of "by the end of the second refueling outage after March 31, 1982" (i.e., June 30, 1983 for Unit 2 and March 30, 1984 for Unit 1). However, due to Crosby's test difficulties in the initial quali-fication program, we were unable to meet this deadline. We requested and were granted an extension of the environmental qualification deadline until May 24, 1985. This date is the end of the next scheduled refueling outage for PBNP, Unit 1. This assumes that the Crosby qualification tests will be satisfactorily completed in time to enable us to install the LISAs on Unit 2 during the fall refueling outage scheduled to start on September 28, 1984.

II.E.1.1 Auxiliary Feedwater System Evaluation The NRC issued the final Safety Evaluation for this item by letter dated April 21, 1982. It stated that upon submittal of proposed Technical

Specification modifications to resolve short term recommendation GS-1, this item would be resolved. Additionally,'in response to concerns relating to this ites, we had committed to installing separate, redundant level instrumentation for both condensate storage' tanks. We also committed to installing a safety grade automatic auxiliary feedwater pump trip on low suction pressure as would occur in the event of failure of the condensate storage. tanks.

The Technical Specification modifications requested in the NRC's safety evaluation were submitted by letter dated April 27, 1982 and approved.in the NRC's letter dated July 27, 1982. .Also,'the separate, redundant' level'

- - _ , _ . _ _ - . - ~

Revision 4 July 9, 1984 instrumentation for both condensate storage tanks has been installed and is operational.

The AFW pump low suction pressure trip is the only outstanding commitment we made in response to this item. Currently, the pressure transmitters for the low suction pressure trip are installed, the Foxboro Spec 200 circuitry is in place, and the trip circuitry is being designed by WE personnel.

II.E.1.2 Auxiliary Feedwater System Initiation and Flow The NRC issued the Safety Evaluation for this item by letter dated May 3, 1982. Contingent upon the completion of some circuitry modifications I

and changes to the Point Beach Technical Specifications, this item was considered resolved. These modifications were necessary, in part, to ensure that operators are alerted when the motor driven AFW pump automatic initiation circuitry is bypassed due to placing a main feedwater pump control switch in the " pull-out" position. Modifications were also required in order to pro-vide indication when the motor-driven pump was out of service due to placing its control switch in the " pull-out" position. Additionally, the AFW flow indication power supplies required upgrading to a battery-backed, class IE source. We also committed to revising the Point Beach Technical Specifications to include periodic testing of the AFW system automatic actuation logic and to revising the test procedure to verify proper operation of the relay coil /

contact combination used to initiate AFW on steam generator low-level. These modifications have been made, the Technical Specifications have been changed, and the test procedure has been revised as we committed. We therefore consider this item closed.

A related commitment, not in response to this item but in response to NRC concerns on AFW system operability, was made in a letter to the NRC dated June 20, 1983. In that letter we committed to modify the opening circuitry for the motor-operated discharge valves for the motor-operated AFW pumps. This modification will ensure that the affected unit's valve will automatically open on automatic initiation of the AFW system should the valve be closed due to testing, startup of the unit, etc. (The valves are normally full open.) This modification was completed on June 29, 1984.

II.E.4.2 1/4 Containment Isolation Dependability-Improved Diverse Isolation As originally designed, Point Beach met the NRC criteria for diversity of isolation and manual, single valve restoration (Reference 3: NUREG-0578, Item 2.1.4, LL Cat. A). Two out of three areas of NRC concern have been previously completed. These were revisions to administrative and operating procedures and modification to the remote control switch for outboard purge valve CV-3212 (Reference 2).

The remaining item was the addition of isolation valves inside con-tainment to piping for letdown, seal water return, and steam generator blow-down. The installation of these inside containment isolation valves was completed for Unit 2 during the spring 1983 refueling and steam generator sleeving outage and for Unit 1 during the fall 1983 refueling and steam generator replacement outage. Since the NRC's Confirmatory Order dated July 12, 1983 lists this item as complete, and our action in response to this item is complete, we consider it closed.

l

l Rsvision 4 July 9, 1984 II.F.1 Accident Monitoring A description of our accident monitoring systems was provided in our submittals to the NRC dated April 26 and July 20, 1982. Currently, all in-struments addressed under this item as described in our previous submittals, are installed, calibrated, and operational using interim power supplies. The instruments will be connected to their final power supplies when the instrument 1 bus upgrade is completed and the Auxiliary Safety Instrumentation Panels (ASIPs) are installed and operational. Additionally, the final display configuration of the accident monitors addressed by items II.F.1.3 through II.F.1.6 will not be completed until the ASIPs are completed. In accordance with our June 26, t

1984 letter, we currently expect to have the ASIPs installed and tested by l October 31, 1984 and the instruments integrated into procedures and operator training on the procedures complete by January 31, 1985.

By letter dated June 21, 1983, the NRC issued its Safety Evaluation for the Containment Pressure Monitoring System (II.F.1.4), Containment Water Level Monitor System (II.F.1.5), and Containment Hydrogen Monitor System (II.F.1.6). The letter stated that these items were resolved for Point Beach.

Although the review of these items did not address environmental qualification, this topic is being addressed in accordance with 10 CFR 50.49.

II.F.2.1 Instrumentation for Detection of Inadequate Core Coolina/Subcoolina Meter j The final subcooling indication system which will meet all of the NRC requirements has been designed as part of the qualified instrumentation system being added to the plant. This added system is intended to provide the means by which the large number of instrumentation changes can be properly incorporated into the existing plant. This new system consists of redundant channels of instrumentation for each unit. The ASIP will be located in the control room at a location which allows for easy viewing of the panel-mnunted display devices. Subcooling display meters will be located on the ASIP. The operability of the final subcooling meter is dependent upon the delivery, installation and operational checkout of the new racks and panels.

Currently, one of two subcooling monitor channels from each unit is connected to a subcooling display temporarily located in an auxiliary rack in the computer room. The second channel from each unit is connected to the backup computer with continuous CRT display available in the control room.

Additionally, due to the past delays in the design and delivery of the new plant process computer system, we have decided to purchase the equipment necessary to make the subcooling indication system fully operational without the new computer. This equipment will be in a configuration which will allow it to be either an interim or a final subcooling indication system.

The final configuration will be determined at a later date. We expect the system to be fully operational in late 1984.

II.F.2.3 Reactor Vessel Water Level Wisconsin Electric submittals dated October 20, 1981, July 28, 1982, January 19, 1983 and March 21, 1983 provided detailed descriptions, answers to NRC questions, and analyses on our Reactor Vessel Water Level system (RVWLS).

Currently, all connection. for the RVWLS have been made up through the Foxboro C

- ~y --,,~m e-- w,- .--~e - . w ~

I l

Revision 4 July 9, 1984 l racks. We have one channel of uncompensated level from each unit connected to the backup computer with continuous display available in the control room.

Uncompensated level will become available on the ASIPs when they become operational in late 1984. compensated level will become available when the new equipment noted in Note II.F.2.1 is installed in late 1984.

II.K.3.5 Automatic Trip of Reactor Coolant Pumps During Loss-of-Coolant Accident The criteria for resolution of this item were established in Generic Letter 83-10d dated February 8, 1983. Reference 143 presented our plan for demonstrating compliance with tnose criteria. To summarize this plan, Westinghouse and the Westinghouse Owner's Group (WOG) undertook a two part program to address the requirements of Generic Letters83-10c and d.

In the first part of the program, revised RCP trip criteria were developed to provide an indication to the operator to trip the RCP's for small break LOCA's requiring such action while allowing continued RCP operation for steam generator tube ruptures, less than or equal to a double-ended tube rupture. The revised RCP trip criteria were incorporated into Revision 1 of the Emergency Response Guidelines. Part Two of the program provided the required justification for manual RCP trip. WOG 1etter 0G-110 dated 12/1/83 transmitted WOG report " Evaluation of Alternate RCP Trip Criteria" which presented the criteria and methodology for RCP trip in response to Section I of Generic Letter 83-10d. WOG letter OG-117 dated 3/12/84 transmitted the WOG report " Justification of Manual RCP Trip for SBLOCA Events." Our final response to this item was submitted by letter dated May 1, 1984.

II.K.3.30/31 Small Break LOCA Methods / Compliance With 10 CFR 50.46 The most recent correspondence on these two items was NRC Generic Letter 83-35 dated November 2, 1983. It stated that the requirements of Item II.K.3.31 for our currently approved Small Break LOCA model can be satisfied by our submittal of a plant-specific analysis which demonstrates that current SBLOCA analyses using previously approved evaluation methods are more limiting than analyses using revised II.K.3.30 models. This can be done on a generic basis through an owner's group with the results submitted individually by the licensee. Westinghouse has submitted a revised SBLOCA model for NRC approval.

Wisconsin Electric, as part of the Westinghouse Owners Group, is waiting for the NRC Safety Evaluation of this model before proceeding any further towards the completion of either of these items.

III.A.1.2 Upgrading Emergency Support Facilities The status of our emergency response facilities is described in our submittals dated March 8,1984 and April 15 and August 24, 1983. These submittals were in response to Generic Letter 82-33, " Supplement 1 to NUREG-0737 Requirements for Emergency Response Capability."

l l To summarize, we have completed the construction of the Technical Support Center (TSC), the Operational Support Center (OSC), and the Site Boundary Control Center (SBCC). (The Emergency Operations Facility, EOF, is l located in the SBCC.) However, since the final TSC and EOF instrumentation displays are an integral part of the new plant process computer output-1 i

y, - p. ^ - - - -

Ravision 4 July 9, 1984 display system, final operability of the TSC and EOF is dependent upon the computer installation schedule. Additionally, the permanent emergency power supply to the TSC is still expected to be complete by 12/31/84. The current plant parameters displayed in the TSC are as described in our submittals dated March 8, 1984 and March 14, 1980.

III.A.2.2 Emergency Preparedness-Meteorological Data References 13, 38, and 56 provide a description of our Meteorological and Dose Assessment system. Our March 8, 1984 letter provides the current status and schedule for completion. To summarize, both the primary and backup towers are complete. The lake breeze effects tower is expected to be complete by the end of October 1984. Software development for the Meteorological and Dose Assessment program is essentially complete except for integration and checkout on the new computer. The final Meteorological and Dose Assessment system will not be completed until the new computer system is installed.

III.D.3.4 Contrcl Room Habitability NRC letter dated August 10, 1982 transmitted the Safety Evaluation I Report for this item. The SER concluded that the iten was resolved for ?BNP. '

That conclusion was based upon commitments made by members of our staff to complete modifications and recommendations as identified in the SER. The commitments included the addition of portable shielding at the control room  ;

doors and windows, the provision of additional self-contained breathing  !

apparatus units in the control room, and the provision for detection capa-bilities for radioactive iodine and noble gases in the control room HVAC air supply duct. These commitments have been completed. We therefore consider this item closed.

SCHEDULE TABLE POST-TMI REQUIREMENTS FOR OPERATING REACTORS NRC Clariff- Implemen- P8NP cation tation Applica- PBNP Item Shortened Title Description Schedule bility Schedule Remarks Rev I . A.1.1 Shift Technical Advisor 1. On duty Closed (59) Yes Completed On duty since 1/1/80 - Reference 1,12a, 3 25a, and 59

2. Tech Specs Closed (50a) Yes Completed

3. Trained per LL Cat B Reference 12a, 15, 25a, 50a, and 59 Closed (59) Yes Completed Note I.A.1.1.3 and Reference 25a 2

4. Describe long-term Closed (59) Yes Completed Reference 17, 59, and 184 program

• I.A.I.2 Shift Supervisor Delegate non-safety Closed (25a) Yes Completed References 1, 25a, and 44a Responsibilities duties 3 I.A.I.3 Shift Manning 1. Limit overtime 11/1/80 Yes Completed Note I.A.I.3, PBNP Approved Procedure 4.3, 4 Operations Division Personnel Assignments and Scheduling, Rev. O, and References 25a.

44a, 54, 60 and 83

2. Min. Shift Crew Superceded by Yes 3/1/85 Note I.A.I.3 References 4b, 7, 54, 62, 66, 4 10CFR50.54(m) 70, 79, 99, 182, 187 and 209 I.A.2.1 Immediate Upgrading of 1. SRO Experience Closed (25a) Yes Completed RO and SRO Training and 2. SR0s be R0s 1 yr. Closed (25a) Yes Completed Qualifications 3. Three mo. training 2 Closed (25a) Yes Completed Note I.A.2.1.1/4 and Reference 9a on shift

4. Modify training Closed (108) Yes Completed References 25a and 108 3

5. Facility Certification Closed (25a) Yes Completed Note I.A.2.1.5 I.A.2.3 Administration of Training Instructors Complete 8/1/80 Yes Completed Programs SRO Exam Note I.A.2.3 I.A.3.1 Revise Scope and Criteria 1. Increase scope 5/1/80 Yes Completed for Licensing Exams 2. Increase passing grade 5/1/80 Yes Ccapleted

3. Simulator exam 6/1/80 N.A. ---

Note !.A.3.1.3 and Reference 68 %4 July 9, 1984, Revision 4 f

NRC C1:rifi- Implemen- PBNP cation tation Applica- PBNP Item Shortened Title Description Schedule bility Schedule Remarks Rev.

I.C.1 Short-Tere Accident and 1. 58 LOCA Closed (25a) Yes Completed Procedures Review Reference 25a 3

2. Inadequate Core Co. ling

a. Reanalyze and 1/1/81 Yes Completed propose guidelines Generic procedures already submitted 3

b. Revise procedures to NRC - Reference 36, 53, and 64 TBD Yes 1/31/85 Note I.C.1 and References 114, 135a, 143a, 4 144, 154, 155, 175, 181a, 186a, 216, 221, and 227

3. Transients and accidents

a. Reanalyze and 1/1/81 Yes Completed Same as I.C.I.2.a

(- propose guidelines , 3

b. Revise procedures TBD Yes 1/31/85 Note I.C.1 and same references as 4 I.C.I.2.b above I.C.2 shift and Relief Turnover Implement shift turnover Closed (25a) Yes Completed Procedures References 9b and 25a 3 checklist I.C.3 Shift-Supervisor Clearly define superv Closed (25a) Yes Completed Responsibility Reference 25a 3 and oper responsibilities I.C.4 Control-Room Access Establish authority limit Closed (25a) Yes Completed access References 9b and 25a 3 ,

, I.C.5 Feedback of Operating Licensee to implement Closed (54) Yes Completed l procedures P8MP Administrative Procedure 3.15.7 3 Rev. O, approved 12/19/80, " Procedure for Feedback of Operating Experience to Plant Staff" and References 25a and 54 I.C.6 Verify Correct Performance Revise performance Closed (54) Yes Completed l of Operating Activities procedures PBNP Administrative Procedure 4.13, Rev. 9, 3 effective 6/20/80, " Equipment Isolation l

l Procedure" and References 25a and 54 j  !. D.1 Control Room Design Preliminary assessment T80 Yes 10/85 Note I.D.1 and References 114, 144, 175 4 l Reviews and schedule for and 225 correcting deficiencies July 9, 1984. Revision 4 I

t

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NRC Citrifi-Implemen- P8NP cation tation Applica-Item PBNP Shortened Title Description Schedule bility Schedule Remarks Rev, I.D.2 Plant Safety Parameter 1. Description TBD Yes Completed Note I.D.2 Display Console 2. Installed TBD Yes 3

12/31/85* 4 (Projected)

3. Fully implemented TBD Yes 12/31/85* References 114, 144, 175, and 215 4 (Projected)

II . 8.1 Reactor Coolant System 1. Design vents Note II.B.1 Yes Vents Completed References 25a and 47

2. Install vents Nate II.B.1 Yes 12/31/84+

3 (LL Cat B) Note II.B.1, and references 84a 105, 4

3. Procedures 113,121,142,148,181,185,1% and 202 Note II.B.1 Yes 1/31/85 References 181,185, 1 %

II. B. 2 Plant Shielding 1. Review designs Closed (190) Yes Completed Reference 25a and 50 3

2. Plant modifications Closed (190) Yes Completed Note 11.8.2.2 and References 25a, 47, (LL Cat B) 4 68, 89, 98, 136 and 190

3. Equipment qualification Closed (210) Yes Completed Note 11.8.2.3 and References 68 and 210 4 II.B.3 Post Accident Sampling 1. Interim system Closed (189) Yes Completed Reference 25a and 50

2. Plant modifications Closed (189) Yes Completed Note II.B.3 and References 29, 68, 86 (il Cat B) 4 98, 103, 116, 131, 156, 171, 189, 197, 219, and 224 11.8.4 Training for Mitigating 1. Develop training Core Damage Closed (108) Yes Completed Reference 108 program 1

2. Implement program

a. Initial Closed (108) Yes Completed

b. Complete References 23, 47, 68, and 108 3 Closed (108) Yes Completed II.D.1 ~ Reifef 4- Safety Valve 1. Submit program 1/1/80 Yes Completed Test Requ.rements 2. RV and SV Testing References 10a and 50 3 (LL Cat B)

a. Complete testing 4/1/82 Yes Completed References 50 and 71 4

b. Plant-specific 7/1/82 Yes Completed References 50, 71, 87, 117, 170, and 226 report 4

3. Block-Valve testing 7/1/82 Yes N.A. Note II.D.I.3 and References 92, 170, 4 and 226 July 9, 1984, Revision 4

NRC Cirriff- Implemen- PBNP

. cation tation Appilca- PBNP Item Shortened Title Description Schedule bility Schedule Remarks Rev.

II.D.3 Valve Position Indication 1. Install direct Closed (25a) Yes Completed indications of valve Note II.D.3.1 and References 9b 4 and 25a valve position

2. Tech Specs Closed (25a) Yes Completed References 15, 25a and 50a 1 I I . E.1.1 Auxiliary Feedwater System 1. Short tern Closed (74a) Yes Completed Evaluation 2. Long term Note II.E.1.1 and References 40, 49, 4 Closed (74a) Yes Completed 67, and 74a II.E.1.2' Auxiliary Feedwater System 1. Initiation Initiation and Flow a. Control grade Closed (25a) Yes N.A. Reference 25a

b. Safety grade . 4 Closed (25a) Yes Original References 1, 2, 3, 12a 25a and 76 4 Plant Design

2. Flow Indication

a. Control grade Closed (76, Yes Completed Reference 25a, 76 and 200 4 199a)

b. LL A Tech Specs Closed (76, Yes Completed Reference 12a, 15, 76 and 200 4 199a)

c. Safety grade Closed (76, Yes Completed References 44a, 68,76 and 200 4 199a)

II.E.3.1 Emergency Power for 1. Upgrade power Closed (25a) Yes Original Pressurizer Heaters References 1, 2, 3,12a, and 25a 3 Plant Design

2. Tech Specs Closed (50a) Yes Completed Reference 15 and 50a 1 II.E.4.1 Dedicated Hydrogen 1. Design Closed (48) Yes Penetrations Original References 1, 2, 3, 25a and 48 3 Plant Design

~2. Install Closed (48) Yes N.A.

II.E.4.2- Containment Isolation 1-4. Imp. diverse 1/1/80 Yes Completed Dependability isolation Note II.E.4.2.1/4 and Reference 44a & 75 4

5. Cntet pressure setpoint

a. Specify Closed (42) Yes Completed References 26, 42, 44a and 68 3 pressure

b. Modifications Closed (170) Yes N.A. Reference 170

6. Cntet purge valves Closed (25a) Yes Completed Administrative 1y closed - References 25a, 3 44a and 45 July 9, 1984, Revision 4 4

NRC Citrifi- Implemen- PBNP cation tation Applica- PBNP lten Shortened Title Description Schedule bility Schedule Remarks Rn II.E.4.2 Containment Isolation 7. Radiation signal on Closed (170) Yes Original Dependability purge valves Reference Point Beach FFOSAR Section 4.2 Plant Design and Figure 5.2-8 and Reference 170

8. Ted. Specs 12/15/80 Yes Completed References 15 and 45 3 II.F.1 Accident Monitoring 1. Noble gas monitor 12/1/84 Yes 10/31/84*+ Note II.F.1 and References 57, 65, 68, 89 4 130 150, 152, 153, 167, 169, 170, 213, and 229

2. Iodine / particulate 1/1/82 Yes 10/31/84*+

sampling

3. Containment high- 4 1/1/82 Yes 10/31/84*+ Note II.F.1 and References 61, 68, 89, range radiation monitor

4. Containment pressure 130, 136, 146, 162, 170, 213, and 229 1/1/82 Yes 10/31/84*+ Note II.F,1 and Reference 68, 89, 95, 123 4

5. Containment water 133, 136, 146, 162, 165, 170, 213, and 229 1/1/82 Yes 10/31/84*+ Note II.F.1 and Reference 68, 89, 95, 123 4 level 133, 136, 146, 162, 165, 170, 213, and 229

6. Containment hydrogen 1/1/82 Yes 10/31/84*+ Note II.F.I and Reference 68, 89, 95, 123 4 133, 136, 146, 162, 165, 170, 213, and 229 II.F.2 Instrumentation of 1. Subcoc) meter 1/1/80 Yes Detection of Inadequate 2. Tech Spec 12/15/80 See Note II.F.2.1 Note II.F.2.1 and Reference 25a 4 Yes Completed Reference 15 Core Cooling (LL Cat A)

3. Install level 1/1/82 Yes See Note Note II.F.2.3 and Reference 52, 110, 120, 4 instruments II.F.2.3 137, 213, and 215 (LL Cat B)

II.G.1 Power Supplies for 1. Upgrade to emerg Closed (25a) Yes Original Pressurizer Relief Valves, sources References 12a and 25a 3 Block Valves, and Level Plant Design

2. Tech Specs Closed (50a) Yes Completed Indicators References 15 and 50a 1 II.K.1 IE Bulletins 79-05, -06, -08 Closed (33) Yes Completed Reference 33 2 II.K.2 Orders on B&W Plants 8. Upgrade AFW system See II.E.1.1 N.A. ---

9. FEMA on ICS 8/17/79 N.A. ---

10. Safety grade trip 7/1/81 N.A. ---

11. Operator training, Complete N.A. ---

drilling July 9, 1984, Revision 4

m . _ __ _ . . _ _ _ _ . _

NRC

'C1 rifi-Implemen- P8NP cation tation Applica-Item PBNP

• Shortened Title Description Schedule bility Schedule Remarks II.K.2- Orders on B&W Plants 13. Themal-mechanical Closed (230) Yes Completed O

report References 58 and 228 3

14. Lift frequency of See II.K.3.7 PORVs and SVs

15. Effects of slug flow Completed N.A. ---

on OTSGS

16. RCP seal damage Completed N.A. ---

17. Voiding in RCS Closed (205) Yes Completed Note II.K.2.17 and References 25b, 53 3 139, 140, and 205

19. Benchmark analysis a. Closed (34) Eliminated N.A. Reference 34 of seq. AFW flow *

20. System response to Complete N.A. ---

SB LOCA

• II.K.3 Fin.i recommendations, 1. Auto PORV isolation P"~ Task Force a. Des;gn Closed (180) Yes N.R.

b. Test / install Closed (180) Yes N.R. Note II.K.3.1 and References 4, 44a, & 180 3

2. Report on PORY failures Closed (180) Yes Completed

3. Reporting SV and RV Note II.K.3.2 and Reference 19 and 180 3 Closed (69) Yes Completed Note II.K.3.3 and Reference 69 3 failures and challenges

5. Auto trip on RCPS~

a. Proposa 7/1/81 Yes Completed Note II.K.3.5 and Reference 31, 126, 141, 4 modifications 143,1%a,199, 216, and 223

b. Nodify 3/1/82 Yes 1/31/85 Note II.K.3.5

7. Eval of PORV opening 1/1/81 N.A. ---

probability

9. PID controller Closed (43) Yes Completed Controller change made upon initial notification by vendor prior to TNI-2 (References 4, 25a, and 43) 3

10. Proposed anticipatory Closed (43) Yes Original References 4 and 43 trip modifications Plant Design July 9, 1984, Revision 4 r

_.._m__..m----

NRC C1rrifi- Implemen- PBNP cation tation Applica- PBNP

-Ites Shortened Title Description Schedule bility Schedule Remarks g-II.K.3 Final Recommendations, 11. Justify use of Plant Yes M.A.

(Continued) 840 Task Force certain PORV specific As part of the original Plant design '

(dif ferent from TMI-2),' Point Beach has Copes-Vulcan PORVs which corresponds to the Idestinghouse data base, ard, thus,  !

no justification is needed.

12. Anticipatory trip on turbine trip

a. Confirmation or Closed (43) Yes Original Reactor trip caused by turbine trip '

proposed 3 Plant Design bypassed below 50% power as detected by modifications the power range detectors. (References 43 '

b. Modify and 44a)

Closed (43) N.A. ---

13. HPCI & RCIC init levels

a. Analysis 1/1/01 N. A. ---

b. Modify 7/1/81 N.A. ---

14. Iso condenser isol 1/1/87 N.A. ---

modification

15. Isolation of HPCI and 7/1/81 N.A. ---

RCIC modification

16. Challenges and failures to relief valves

a. Study 4/1/81 .N.A. ---

b. Modify 1st refueling N.A. ---

or 1 yr after 4

approval

17. ECCS system outages Closed (174) Yes Completed Note II.K.3.17 and Reference 23, and 174 1.2 July 9, 1984, Revision 4 i

NRC C):rifi- Implemen- P8NP cation tation Item Applica- PBhP Shortened Title Description Schedule bility Schedule Remarks II.K.3 Final Recommendations, 31. Compilance with 1/1/83 or Q

Yes TBD (Continued) 840 Task Force CFR 50.46 1 yr af ter Note II.K.3.31 and Reference 188 staff approval

40. RCP seal damage See II.K.2.16 N.A. ---

43. Effects of slug flow See II.K.2.15 N.A. ---

45. Manual depressurization 1/1/8i N.A. ---

46. Michelson concerns Completed N.A. ---

57. Manual act of A05 TBD N.A. ---

III.A.1.1 Emergency Preparedness, Short-term improvements Completed Yes Shurt Tere Completed

'III.A.1.2 Upgrade Emergency Support 1. Interim TSC, OSC and Facilities Closed (25a) Yes Completed References 9b and 25a EOF

2. Design Reference 15b Yes Completed

3. Modifications Reference 28 Reference 15b Yes 12/31/85* Note III. A.1.2 and References 13, 28, (Projected) 38, 56, 80, 88, 94, 101, 112, 114, 151, 157, 158, 163, 175, 178, 186, 194, and 215 III.A.2 Emergency Preparedness 1. Upgrade emergency Closed (149) Yes Cowleted Note III. A.2.1 and Reference 12b,17a, plans to App. E, 55, and 149 1 10 CFR 50

2. Meteorological data 6/1/83 Yes 12/31/85*

(Projected)

Note III.A.2.2 - References 13, 28, 38 56, 114, 144, 175, and 215

(

!!!.0.1.1 Primary Coolant Outside 1. Leak reduction Closed Yes Containment Completed Currently changing to a yearly testing 1 schedule for both units coincident with refueling outages (References 1, 2, 3, and 25a)

2. Tech Specs 12/15/80 Yes Completed Reference 15 1 ITI.D.3.3 Inplant Iodine Monitoring 1. Provides means to Closed (25a. Yes Completed References 12a and 25a 3 63) determine presence of radiciodine July 9, 1984, Revision 4 i

e t

6

NRC CIrrift- Implemen- PBNP cation tation Applica-Item P8NP Shortened Title Description Schedule bility Schedule Remarks g II.K.3 Final Recommendations, 18. ADS actuation (Continued) 8&O Task Force a. Study 4/1/81 N.A. ---

b. Propose mods 4/1/82 N.A. ---

c. Modification 1st refuel N.A. ---

6 mo after staff approval

19. Interlock recirc pump 7/1/81 N.A. ---

modification

20. Loss of SVC 7/1/81 N.A. ---

21. Restart of CCS and LPCI *

a. Design 1/1/81 N.A. ---

b. Modification 1st refueling N.A. ---

60 eo after staff approval

22. RCIC suction

a. Verify procedures 1/1/81 N.A. ---

b. Modification 1/1/82 N.A. ---

24. Space cooling for 1/1/82 N.A. ---

HPCI/RCIC modifications

25. Power on pump seals

a. Propose mods Closed (124) Yes None

b. Modification 3 Closed (124) Yes N.A. Note II.K.3.25 and References 106, 119 & 124

27. Com ref. level 7/1/81 N.A. ---

28. Qual of ADS 1/1/82 N.A. ---

accumulators

29. Performance of 4/1/81 N.A. ---

isolation condensers -

30. 58 LOCA methods

a. Schedule outline 11/15/80 Yes TBD

b. Model 4 1/1/82 Yes TBD Note II.K.3.30 and References 69a, 91 & 188

c. New analyses 1/1/83 or Yes TBD 1 yr after staff approval July 9, 1984, Revision 4

____ _ --- 9

NRC CI' r t f i- Implemen- PBNP cation tation Applica- PBNP Item Shortened Title Description Schedule bility Schedule Remarks Ry

2. Modifications to Closed (63) Yes Completed accurately measure 1 Note III.D.3.3 - Reference 12a, 25a, 3 7 and 63 III.D.3.4 Control Room Habitability 1. Review Closed (93) e s Completed Note III.D.3.4 and References 12, 13, 16, 93 and 136

2. Modification Closed (93) Yes Completed Note III.D.3.4 and References 12, 13, 16, 93, 4 136 and 210 k

July 9, 1984, Revision 4 1

.o

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