View source for B12281, Forwards Updated Info Re Status of Implementation of Each Regulatory Requirement/Improvement in NRC Safety Issues Mgt Sys

{{Adams
| number = ML20211H520
| issue date = 10/02/1986
| title = Forwards Updated Info Re Status of Implementation of Each Regulatory Requirement/Improvement in NRC Safety Issues Mgt Sys
| author name = Opeka J
| author affiliation = CONNECTICUT YANKEE ATOMIC POWER CO., NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES
| addressee name = Grimes C
| addressee affiliation = NRC OFFICE OF NUCLEAR REACTOR REGULATION (NRR)
| docket = 05000000, 05000213, 05000245, 05000336
| license number = 
| contact person = 
| case reference number = TASK-***, TASK-TM
| document report number = B12281, NUDOCS 8611050178
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE, UTILITY TO NRC
| page count = 44
}}

=Text=
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              .           [" "j$~.                                       (203) 665-5000 October 2,1986 Docket Nos. 50-213 50-245 50-336 B12281 Office of Nuclear Reactor Regulation Attn: Mr. C. I. Grimes, Director Integrated Safety Assessment Project Directorate Mr. A. C. Thadani, Director PWR Project Directorate #3 U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Gentlemen:
Haddam Neck Plant Millstone Nuclear Power Station, Unit Nos.~ l and 2 NRC Safety Issues Management System                    .
In letters dated April 28,' 1986(l) and May 1, 1986,(2) the NRC Staff indicated they are working on a long-term program, which will improve the documentation on the status of power reactor licensees' implementation of approved regulatory requirements / improvements.            This effort, previously titled " Generic Issues Management Tracking Systems" (GIMTS), is now called " Safety Issues Management System" (SIMS). In a {{letter dated|date=June 13, 1986|text=letter dated June 13, 1986}},(3,1 the Connecticut Yankee Atomic Power Company (CYAPCO) and Northeast Nuclear Energy Company (NNECO) submitted a list indicating the status of each regulatog requirement /impr9vement as of June 13, 1986. In letters dated June 27,1986m and July 30,1986,\5) CYAPCO and NNECO submitted additional information.
(1) D. B. Osborne letter to 3. F. Opeka, "NRC Generic Issues Management Tracking System," dated April 28,1986.
(2) C. I. Grimes letter to 3. F. Opeka, "NRC Generic Issues Management Tracking System," dated May 1,1986.
(3) 3. F. Opeka letter to C. I. Grimes and A. C. Thadani, "NRC Generic Issues Management Tracking System," dated June 13,1986.
(4) 3. F. Opeka letter to C. I. Grimes and A. C. Thadani, "NRC Generic Issues                               ;
Management Tracking System," dated June 27,1986.                                                       1 (5) 3. F. Opeka letter to C. I. Grimes and A. C. Thadani, "NRC Generic Issues                                 L g g Management Tracking System," dated July 30,1986.
8611050178 861002 PDR ADOCK 05000213 P                          PDR

           .e           .
It has been and remains the intent of CYAPCO and NNECO to continue our efforts to investigate and provide additional information with respect to the remaining issues.
Since the time of the Reference (5) submittal, telephone discussions with the NRC Staff have provided needed clarification on many issues and resulted in the identification of documentation serving 'as references to completion dates.
Accordingly, CYAPCO and NNECO are hereby providing an updated response which is included as an attachment to this letter. Additions and changes to the previous submittal in Reference (5)-are noted with change bars. All of the.
licensing ' actions for Millstone Unit No. 2 have been addressed. Additional interactions between CYAPCO/NNECO and the NRC Staff of a similar nature to 4
those occurring recently will be necessary to verify the documentation that closes out the remaining issues in the SIMS listing for the Haddam Neck Plant and Millstone Unit No.1.
It is the perception of CYAPCO and NNECO that the significance of SIMS in relation to ongoing regulatory activities is increasing.- CYAPCO and NNECO
:                   intend to be responsive to this perception by continuing.our efforts to provide documented completion dates for each issue on an accelerated basis. Further, we are ~taking additional steps to validate that. the completion dates and references previously provided in fact represent " final closure" of the issue in question. ' Should these additional steps result in any changes to data previously provided, we will update you accordingly.
4
                  .If you have any questions, please contact us.
Very truly yours, CONNECTICUT YANKEE ATOMIC POWER COMPANY
,                                                         ' NORTHEAST NUCLEAR ENERGY COMPANY
!                                                           3. F. Opeka '
Senior Vice President i
!                                                           By: C. F. Sears Vice President i
s e

s t Docket Nos. 50-213 50-245 50-336-B12281 Attachment Haddam Neck Plant Millstone Nuclear Power Station, Unit Nos. I and 2 Safety Issues Management System -
Updated Information October,1986

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R-1208751-001                          REGULAT0RY                  INF0RMATION                        TRACKINO SYSTEM                     PAGE 140, s 202 FACI'LITY                 IMP ~LEMENTATION                                                03/31/86.
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m.

Connecticut Yankee Footnotes 4
: 1. Closed, 2/26/81, D. M. Crutchfield letter to W. G. Counsil, 

==Subject:==

                  ;" Inservice Inspection and Valve Testing Program." Safety Evaluation on License Amendment No. 37. Complete changes to 10CFR50.55A(8) on 7/27/76.
: 2. A. Schwencer letter to D. C. Switzer, dated 12/14/77,' 

==Subject:==
 "Haddam Neck Plant." Letter grants relief on an interim basis for ISI, pending completion of NRC detailed review.
: 3. Closed, 1/1/86, RETS effective'.         Our 4/22/86 letter:      Annual Environmental Operating Reports currently in Administrative Technical Specifications.
4.
5.
: 6. Closed,12/2/80, D. M. Crutchfield letter to W. G. Counsil, Docket No. 50-213, issued. Amendment No. 36 to the Haddam Neck Plant. NRC Internal Memorandum, dated 8/18/86, R. L. Erich, Jr., to Project Directors and Project Managers, 

==Subject:==
 " Clarification of MPAs for SIMS."
: 7. Closed, 12/19/83, NRC letter to W. G. Counsil (A03694); NRC Internal .
Memorandum, dated. 3/18/86, R. L. Erich, Jr., to Project Directors and Project Managers, 

==Subject:==
 " Clarification of MPAs for SIMS."
: 8. NRC Internal Memorandum, dated 8/18/86, R. L. Erich, Jr., to Project Directors and Project Managers, 

==Subject:==
 ~ " Clarification of MPAs for SIMS."
: 9. Closed, 4/14/82, Inspection 50-213/82-03; NRC Internal Memorandum, g 8/18/86, R. L. Erich, Jr., to Project Directors and Project Managers,     8

==Subject:==
 " Clarification of MPAs for SIMS."
: 10. Completed, D. M.- Crutchfield letter to W. G. Counsil, dated 12/29/83, issued Amendment No. 37 to Operating License DPR-61 approving . l Inservice Testing Program, i
11.
: 12. Incomplete. ISAP topic, submittal should be forthcoming fall 1986.
: 13. Incomplete. Last submittal was 3. F. Opeka letter to 3. A. Zwolinski, dated 7/9/86, (Bil584), titled Proposed Revisions          to Technical Specifications - Reponse to Generic Letter No. 83-43. Presently awaiting amendment to be granted.
l            14. Incomplete.      Projected date for next submittal is 7/29/86.       Last l                  correspondence was 3. F. Opeka letter to C. I. Grimes, dated 2/18/86, j                  ATWS Rule Schedule Required by 10CFR50.62 (A05442).
i i

e  s Connecticut Yankee Footnotes
: 15. 3. F. Opeka letter to C. I. Grimes, dated 1/23/86, completed pending NRC -
review.
16.
17.
: 18. - Closed, 11/16/81, D. M. Crutchfield letter to W. G. Counsil (A02117).
: 19. Closed, 4/24/80, D. L. Ziemann letter to W. G. Counsil, Docket No. 50-213. This amendment authorized changes that enhanced low temperature
        .over-pressure protection.
: 20. Closed,2/26/80, D. L. Ziemann letter to W. G. Counsil (A00881).
: 21. Closed, 6/16/80, G. C. Lainas letter to W. G. Counsil, 

==Subject:==
 " Charging Pump Vibrations Safety Evaluation."
: 22. Closed, 7/10/80, D. M. Crutchfield letter to W. G. Counsil, Su'      b ject: l
         " Control Rod Thimble Wear."
: 23. . Closed, 2/13/81, W. G. Counsil letter to D. G. Eisenhut, 

==Subject:==
l
         " Emergency Planning," submitted updated emergency plans.
: 24. Incomplete.                                                                 .l Closed,- 1/3/79, W. G. Counsil letter to D. L. Ziemann, Containment
                                                                           ~
25.
Purging.
: 26. Closed, 2/23/82, C. Tropf. memorandum to all ORPM, this task was               -
removed from the MPA list.
: 27. Incomplete.
28.. Closed,7/9/82, D. M. Crutchfield letter to W. G. Counsil (A02632)
: 29. Clos'ed,10/8/80, D. M. Crutchfield letter to W. G. Counsil.
: 30. Closed, 12/18/81, D. M. Crutchfield letter to W. G. Counsil, LS05-81          056.
: 31. Not applicable.
32.
: 33. Not app!! cable, no letters were sent to licensees, deleted from the multi-plant program by NRC internal memo, to all DOL Assistant Directors and Branch Chiefs, from D. G. Eisenhut, dated 11/13/80.
: 34. Closed, 11/20/81, D. M. Crutchfield letter to W. G. Counsi', Fire Protection System - Haddam Neck, ~ Amendment No. 45, consists of changes to Technical Specifications in response to application dated 6/2/81.

Connecticut Yankee Footnotes
: 35. Closed, 11/14/84,3. A. Zwolinski letter to W. G. Counsil (A04500).
36.
: 37. - Closed, 6/18/79, W. G. Counsil letter 'to D. L. Ziemann, 

==Subject:==

           "Feedwater Lines."
  - 38. Closed,11/5/79, W. G. Counsil letter to B. H. Grier, 

==Subject:==
 "Feedwater System Piping."
   ' 3 9.~
: 40. Closed, 2/76/81, D. M. Crutchfield letter to W. G. Counsil, 

==Subject:==

           " Primary Isolation Coolant System Pressure Isolation Valves," in Amendment No. 37 to Operating License DPR-61.
: 41. Closed, 10/28/81, W. G. Counsil letter to D. M. Crutchfield (A01952).
: 42. Closed, 3/23/82, D. W. Crutchfield letter to W. G. Counsil (A02386).
: 43. Closed, 3/19/82, D. W. Crutchfield letter to W. G. Counsil (A02380).
44.
: 45. Closed, 4/25/86, J. F. Opeka letter to E. C. Wenzinger, 

==Subject:==

           " Environmental Qualification Review."
: 46. Closed by internal NRC memorandum from M. B. Fairtile to All ORPMs, dated 7/28/82, 

==Subject:==
 "Close-Out of MPA 61 - NRR Portion of Review of IE Bulletin in 79-2."
47.
: 48. D. M. Crutchfield letter. to W. G. Counsil, dated 8/27/81, Implementation Schedule Acceptance.
: 49. Closed, 7/26/83, D. W. Crutchfield letter to W. G. Counsil (A03418).
: 50. Closed, 4/28/83, D. W. Crutchfield letter to W. G. Counsil (A03220).
: 51. Not applicable, no letter sent to licensees, turned down by CRGR.
: 52. Closed,5/30/84, W. G. Counsil letter to NRC (A03776).
: 53. Issue date 3/20/85, approval date 3/20/85, 3. A. Zwolinski letter to W. G. Counsil (A04762).
: 54. Incomplete, last correspondence was 3. F. Opeka letter to 3. A. Zwolinski, dated 3/9/85, Generic Letter 83-28, Request for Additional Information.
: 55. Issue date 2/21/86, approval date 2/21/86, F. M. Akstulewicz letter to
: 3. F. Opeka (A05596).
: 56. Issue date 10/16/85, approval date 10/16/85,3. A. Zwolinski letter to J. F. Opeka (A05321).

Connecticut Yankee Footnotes
: 57. Closed, 2/21/86, F. M. Akstulewicz letter to 3. F. Opeka, 

==Subject:==
 " Post-Maintenance Testing and Reactor Trip System Reliability."
: 58. . Issue -date 7/1/85, approval date 7/1/85, 3. A. Zwolinski letter to
: 3. F. Opeka (A05024).
: 59. Issue date - 11/28/84, approval date ' 11/28/84, J. A. Zwolinski letter to -
: 3. F. Opeka (A04513).
60.~ ' Will be completed with our standard technical specification conversion.
: 61. Issue date 7/3/85, approval date 7/3/85, 3. A. Zwolinski letter to
: 3. F. Opeka (A05043).
: 62. Incomplete.
: 63. Issue date 2/21/86, approval date 2/21/86, F. M. Akstulewicz letter to
                    ~
: 3. F. Opeka (A05596).
     ~64. Issue date 10/16/85, approval date 10/16/85,3. A. Zwolinski letter to
: 3. F. Opeka (A05321).
: 65. Incomplete, last correspondence was 3. F. Opeka letter to 3. A. Zwolinski,
            ' dated 5/9/85, Generic Le_tter 83-28, Request for Additional Information.
: 66. Issue date .11/28/84, approval date 11/28/84,3. A. Zwolinski letter to W. G. Counsil (A00513).
: 67. Issue date 2/21/86, approval date 2/21/86, F. M. Akstulewicz letter to
                        ~
: 3. F. Opeka (A05596).
: 68. Incomplete, last correspondence was 3. F. Opeka letter to 3. A. Zwolinski, dated 10/18/85, Response to Generic Letters 85-09 and 82-28, Item 4.5.3.
    ' 69.
: 70. Closed, 8/5/82, D. M. Crutchfield letter to W. G. Counsil. No action required. Decision on technical specifications deferred to SEP.
: 71. Not applicable, no modifications were required as a result of NUREG-0577, Revision 1 (October,1983).
: 72. Closed, date 12/26/79, D. L. Ziemann letter to W. G. Counsil, Docket No. 50-214.
73.
74.
: 75. Closed, 6/28/85, H. L. Thompson letter to All Licensees, closing Phase II of " Control of Heavy Loads" for all plants.
76.
: 77. Closed, 11/29/84, W.' G. Counsil letter to T. E. Murley, 

==Subject:==

            " Refueling Cavity Pool Seal."

Connecticut Yankee Footnotes
: 78. Issue date 2/1/84, approval date on-going, NRC letter to W. G. Counsil         -
(A03859).
: 79. Closed,'ll/8/77, D. C. Switzer letter to A. Schwencer, 

==Subject:==
 " Fission Gas Release," concludes no LOCA impact due to fission gas release.
: 80. Not applicable, closed by NRC internal memo dated 2/2/84, IE Information Notice 79-22, issued by no modifications necessary.
: 81. Closed, 12/21/81, D. W. Crutchfield letter to W. G. Counsil (A02176).
: 82. W. G. Counsil letter to    D. G. Eisenhut, dated 2/4/85, (A04190) transmitting information requested by Generic Letter 84-15.
83.
: 84. I. A. I .1, D. M. Crutchfield letter to W. G. Counsil, dated 3/31/82, CYAPCO's Responses to NUREG/0737 Item              I. A . I .1 Shift Technical Advisor, was complete.
Information in (2) letters:
W. G. Counsil letter to D.' M. Crutchfield, dated 2/19/82.
W. G. Counsil letter to D. G. Eisenhut, dated 12/31/80.
: 85. I.A.I.3, Amendment 71 to Facility Operating License No. DPR-61, dated 12/10/85. ' Response to application dated 7/9/85.
: 86. I.A.2.1, D. M. Crutchfield letter to W. G. Counsil, dated 12/15/82. NRC
             - contractor's review of our letters dated 8/15/80,10/30/81 and 4/28/82.
: 87. I.C.I.2/3.A, Incomplete. Will be done per order from NRC. Projected
 ,            dated 9/1/86.
: 88. I.C.I.2/3.B, Incomplete. Will be done per order from NRC. Projected dated 9/1/86.
: 89. I.C.5, D. M. Crutchfield letter to W. G. Counsil, dated 2/8/82, finds procedure acceptable. I.C.5 resolved.
: 90. I.C.6, .D. M. Crutchfield letter to W. G. Counsil, dated 2/8/82, finds procedure acceptable.1.'C.6 resolved.
: 91. I.D.I.1, J. F. Opeka letter to C. I. Grimes, dated 2/28/86, Submittal of the Control Room Design Review (CRDR) Program Plan and a schedule for the submittal of the CRDR summary report.
: 92. I.D.2, Incomplete. Reference our submittal on 5/15/86. Projected dated 3/25/88.
1
: 93. II.B.1, D. M. Crutchfield letter to W. G. Counsit, dated 9/6/83. Complete,
!             based on requirements and promulgation of 10CFR50.44(c)(3)(iii).
i

s   's
                                                                                             ' Connecticut Yankee Footnotes
: 94. II.B.2, R. W.-  Startostecki _ letter to W. G. Counsil, dated 3/11/83,
               ' Inspection Report #83-12. No violations observed.
               " Completed, D. W. C letter to W. G.~ Counsil, dated 9/27/83 (A03419).
: 95. II.B.3, D. M. Crutchfield letter to .W. G. Counsil, dated 6/5/84, safety evaluation: all of 11 criteria are acceptable. (A04094) .
: 96. II.B.4.1 (see #86).
97.. II.D.1, 3. A. Zwolinski letter to W. G. Counsil, dated 10/29/84, requesting -
additional information.          Sent 4/15/E5 from     W. G. Counsil to
: 3. A. Zwolinski. =
: 98. - II.E.1.1, D. M. Crutchfield letter to W. G. Counsil, dated 11/9/82, item complete, safety evaluation enclossd.
: 99. II.E.1.2.1, AFWS (automatic initiation), D. M. Crutchfield letter to W. G. Counsil,-dated 10/5/82. Safety evaluation - comply with the Staff's -
long-term safety grade requirements.
1100. II.E.1.2.2, AFWS (flow indication), see #99.
101. II.E.4.1, D. M. Crutchfield letter to W. G. Counsil, dated 9/3/81.
5/80 - Sent documented acceptance of Item 2.1.5 (NUREG-0578), also satifies II.E.4.1.
102. II.E.4.2, -Completed, D. M. Crutchfield letter to W. G. Counsil, dated 10/4/82 (A02804).
103. II.F.1.1, R. A. Clark letter to W. G. Counsil, dated .11/23/81. Our letter of 10/16/81 provided necessary information to resolve deviations from NUREG-0737 Items II.F.1.1 and II.F.1.2.
104. II.F.1.2, See - # 103.
105. II.F.1.3, R. A. Clark letter to W. G. Counsil, dated 1/15/82. Reviewed our submittals, no technical deviations from stated positions requested (we; requested none).
106. . II.F.1.4, T. T. Martin letter to W. G. Counsil, dated 6/26/84. Safety inspection by Dr. P. K. Eapen, 5/21-25/84. No violations observed. .
107. II.F.1.5, 3. A. Zwolinski letter to 3. F. Opeka, dated 7/9/85, safety evaluation - concerns resolved (same letter applies above).
108. II.F.I'.6, Reference 1: W. A. Paulson letter to W. G. Counsit, reviewed our 8/6/82 and 4/9/84 submittals. The safety evaluation concluded all but the requirement for redundancy was met for Item II.F.16. Reference 2:
W. A. Paulson letter to W. G. Counsil, dated 7/30/84. Reference' 3:           .
Incomplete due to Regulation Guide 1.97.

~
_7__
Connecticut Yankee Footnotesi 109.1 II.F.2, F. M. Akstulewicz letter to 3. F. Opeka, dated 12/12/85. Staff and-consultants at the Oak Ridge National Laboratory reviewed our submittals -
of : 3/11/83 and 2/1/85.. The ICC system design is acceptable and consistent with requirements of NUREG-0737 Item II.F.2.
110. . II.K.2.13,' D. M. Crutchfield letter to W. G. Counsil, dated 6/13/84, safety evaluation included.: Complete.
111.-   II.K.2.17,' D. M. Crutchfield letter- to ' W. G. Counsil, . dated 12/22/83,.
                . reviewed the Westinghouse Owner's Group April 20, 1981 submittal on the St. Lucie cooldown event. Voids generated are. accounted for. Voids will not result in unaccepable consequences. .
112. II.K.3.1, D. M. Crutchfield to W. G. Counsil, dated 9/9/83, safety evaluation included. Requirements met.
I13. II.K.3.2, dated 9/9/83, see #112.
        ~114. II.K.3.3, D. M. Crutchfield letter to W. G. Counsil, dated 3/8/82, item resolved.
115. ' II.K.3.5, 2/8/83, Evaluated the analyses of LOFT Test L3-6 performed by C. E. Owners Group:- The evaluations acceptably predict test results.
Reference 2/22/83 letter. Still open under #132.
116.-   II.K.3.9, D. M. Crutchfield letter ' to W. G. Counsil, dated 11/30/81, reviewed our submittals of 6/10/80 and 12/31/80. CY doesn't have a PID controller, item not applicable.
117. II.K.3.10, Letter of 6/10/80.         Item not applicable (applies only to Westinghouse PWR licensees who have applied to the NRC to modify the turbine / trip anticipatory trip scheme.
118. II.K.3.12, Our 6/10/80 and 12/31/80 letters confirm CY - has an anticipatory reactor trip on            turbine trip, in accordance with item II.K.3.12. Item resolved.
119.. II.K.3.17, D. M. Crutchfield letter to W. G. Counsil, dated 8/8/83, reviewed our report detailing outage dates and length of outages.
Requirement met. Safety evaluation included.
120. II.K.3.25, Incorporated in ISAP. - ' Reference 3. F. Opeka letter to
: 3. A. Zwolinski, dated 6/3/85.-
121. II.K.3.30 (SB LOCA Methods), 3. A. Zwolinski letter to W. G. Counsil, dated 3/25/85.        NU submitted 2 topical reports dated 8/23/84:
Supplement .1, NULAP-5, a Fortran IV digital computer program for nuclear- steam . supply system, blowdown and fuel heatup; calculative methods for NU Small -Break LOCA ECCS Evaluation Model. We requested information (reports) be withheld from public disclosure pursuant to 10CFR2.790. Still under review by Staff _ our submittal.
122. II.K.3.31, Still under review by Staff - our submittal.

Connecticut Yankee Footnotes 123. II.A.I.2, Technical Support Center, W. A. Paulson letter to W. G. Counsil, dated 9/11/84. Reviewed our request to locate the TSC outside the plant protected area.       Want additional information. Operational /pending modifications. Reference order dated 6/12/84.
124. Ill.A.I.2, Operational Support Center, operational /pending modifications.
Reference order dated 6/12/84.
125. III. A. I .2, Emergency Operations Facility, D. G. Eisenhut . lette to W. G. Counsil, dated 6/7/84. Alternate location of EOF (Corporate Emergency Operations Facility in Berlin) is acceptable.
126. III. A. I .2,  Nuclear Data Link, NUREG-0737.                             Not applicable.
Implementation never required by NRC.
127. III.A.2.'1, Emergency Plan Upgrade to meet rule, D. M. Crutchfield letter to W. G. Counsil, dated 5/13/83. Item complete.
128. lil.A.2.2, D. G. Eisenhut letter to All Licensees, dated 12/17/82, 

==Subject:==

Supplement I to NUREG-0737, Requirements for Emergency Response Capability, affects III.A.2.2. Letter provides additional clarification regarding meteorological data. Superseded by Generic Letter 82-33, page 13 of Attachment 1. No longer a requirement for III.A.2.2.
129. III.D.3.3, D. M. Crutchfield letter to W. G. Counsil, dated 6/29/82. No further review planned if we meet the position to improve in-plant iodine instrumentation. W. G. Counsil response to D. M. Crutchfield, dated 7/20/82. CYAPCO meets position. No deviations requested.
130. III.D.3.4, 3. A. Zwolinski letter to 3. F. Opeka, dated 7/1/85, Amendment #63. License No. DPR-61 (changed the completion date).
131. 1.D.I.2, Incomplete.
132. II.K.3.5, W. G. Counsil letter to 3. A. Zwolinski, dated 12/20/84.
Resubmitted the topical entitled " Calculative Methods for the NU Small Break LOCA ECCS Evaluation Model."               The submittal completes CYAPCO's response to TMI Action Plan items II.K.3.5, II.K.3.30 and II.K.3.31. Still under review.
l
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I
                                                                                                                                                            -A R-1208751-001                    REGULAT0RY           INF0RMATION               TRACKING    SYSTEM                     PAGE NO                    268 FACILITY           IMPLEMENTAT. ION                                                          03/31/86' FACILITY: MILLSTONE 1 PLANT LOCATION: 5 MI SH OF NEN LONDON, CONN          LICENSED PONER: 2011 MNT            PROJECT MANAGER: J. SHEA DOCKET NUMBER: 050-80245                             DESIGN POWER:    0660 MNE           BRANCN CHIEF      C. GRIMES AOCH/ ENGINEER: EBASCO                               NSSS VEN3OR:    GE                  LIC ASSISTANT:    P. ANDERSON IE INSPECTOR      T. SHEDLOSKY LIC ACT                  LICENSEE TAC NO. MPA 3                  TITLE                                    COMPLETE            STATUS       MIf M08294      A-01   10 CFR 59.55 A(G) - ISI                                                                      g 09/19/79C
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M10012      A-10   CONTINGENCY PLANNING                                                                  t,{ , g _ Q 04/05/83C Q                                             g M19408      A-11   GUARD TRAINING PLANS                                    04/OS/82C
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M12137      B-16   EMERGENCY PLANNING AND REVISIONS                       04/01/81C Q        ([ _ g (
M08417      B-17   TECH SPEC SURVEILLANCE FOR HYDRAULIC SNUSOERS          12/28/81C Q      g_p gg                                  g M10386      B-20   CONTAINMENT LEAKAGE DUE TO SEAL DETERIORATION          10/25/80C e

F 3
s R-1208731-901                   REGULATORY            INF0RMATION            TRACKINO   SYSTEM                    PAGE NO. 269, FACILITY         IMPLEMENTATION                                         03/31/86 MILLSTONE 1                 (CONTINUATION)
LIC ACT                  LICENSEE
  ,      TAC NO. MPA 9                   TITLE                                 COMPLETE           STATUS         DAIE        hGdMk M10308    B-21     LOSS OF 125-V DC BUS VOLTAGE HITN LOSS OF ANNUNCIA  02/09/82C                                         ,y M08415    B-22     TECN SPEC SURVEILLANCE REQUIREMENTS FOR MECNANICAL  12/28/81C
{_         }Q -g- g g        y M10033 M42612 3-23 B-24 DEGRADED GRID VOLTAGE VENTING AND PURGING CONTAINMENTS HNILE AT FULL POW 06/01/83C 02/25/85C 1       pp gg,(g              g 1            7-3-gg           g(g M10192    3-24     VENTING AND PURGING CONTAINMENTS HNILE AT FULL PDH  10/25/80C             C          7. 3 - g b       gg M08412    B-25     BWR FEEDWATER N0ZZLE CRACKING                       06/09/83C
{        g _(j _ g          g M10949    B-27     REVIEN RESPONSES TO IE BULLETIN 78-03 (OFFGAS EXPL  10/01/80C l       MI1017    B-29 C-        3~'A-78          21 BWR FEEDHATER PUMP TRIP                             11/30/78C Ml1786 Q         g g. g.g           g        g B-40 ' PIPE SUPPORT BASE PLATES                              01/23/81C 2Cg M11116    3-41     FIRE PROTECTION - FINAL TECN SPECS (INCLUDES SER S  07/29/82C C        7 3 g          33 M06043    3-41 M11705    B-42 FIRE PROTECTION - FINAL TECN SPECS (INCLUDES SER S TMI FOLLON UP - ALL PLANTS 09/26/78C 07/10/81C g       gg.                           l
    , M12421       3-44     LESSONS LEARNED IMPLEMENTATION                      05/02/80C
                                                                                               ~
y M30544 M30545 5-44 B-44 LESSONS LEARNED IMPLEMENTATION                      04/18/80C           1        L1-1 & SO            M LESSONS LEARNED IMPLEMENTATION                      04/18/80C            Q       Lj- { ((- 3Q        y i
M30506    B-44     LESSONS LEARNED IMPLEMENTATION                      04/18/80C            Q       L{- g p g           y M30547    B-44 M30508    B-44 LESSONS LEARNED IMPLEMENTATION LESSONS LEARNED IMPLEMENTATION 04/18/80C            [       Lt - 19/ 20         m 04/18/80C Q       l\ - j $- QQ        y M30509    B-44     LESSONS LEARNED IMPLEMENTATION                      04/18/80C            {       Q- g g - gg         3Cg
        'M30550    B-44     LdSSONS LEARNED IMPLEMENTATION                      04/18/80C            Q        S g q - hC           Lp M30551    B-44     LESSONS LEARNED IMPLEMENTATION                      04/18/80C                    q, g p gQ l
Q                             qg i
M30552    B-44     LESSONS LEARNED IMPLEMENTATION                      04/18/80C
{       Q - g g , g,          g M30553    B-44     LES$3NS LEARNED IMPLEMENTATION                      04/18/80C Q      tj - g K _ g

T R-1208731-001                         REGULAT0RY             INF0RMATION           TRACKING SYSTEM                      PAGE NO t   270 FACILITY        IMPLEMENTATION                                         03/31/86' MILLSTONE 1                       (CONTINUATION)
LIC ACT                LICENSEE
,           TAC NO. MPA 3                         TITLE                                 COMPLETE         STATUS        MIf.           -(CCA GD M30554     B-44         LESSONS LEARNED IMPLEMENTATION                        04/18/80C
{         q. 4 g"Q            Lg(g M30555     B-44         LESSONS LEARNED TMPLEMENTATION                        04/18/80C
{          tg, g g M12918     B-45        NASN 1400 EVENT V, " PRIMARY COOLANT SYSTEM PRESSUR    02/25/81C g
M42079     B-46         ANALYSIS OF TURBINE DISC CRACKS                       05/15/80C         Q         l_1p gO               Lp M12698     B-47                                                               07/30/80C ECCSs CLAD SHELLING AND RUPTURE G        Q g p gQ              (g M12762     B-48        ADEQUACY OF STATION ELECTRIC DISTRIBUTION VOLTAGE      04/19/83C          (        Q gq.g                 LQ M10704     B-56        CONTROL RODS FAILURE TO INSERT. BHR                    06/15/81C Q       g g_g                   g M42210     B-58        SDV CAPABILITY                                         01/09/81C
{         ,,,g y gg i           M47431     B-58        SDV CAPABILITY                                         04/21/83C M42913     3-59        MASONRY HALL DESIGN                                    04/30/86 52.
{         g g F6               S3 Ma2523     3-60         ENVIRONMENTAL QUALIFICATION                           07/30/85C
;                                                                                                            1          $ g6 l              3([
M42684     B-61        LOSS OF NON CLASS IE 18C PDHER                         07/28/82C
                                                                                                                                             $g M42755     B-62         ESF RESET CONTROL DESIGN DEFICIENCY                   07/24/81C g      g g        gg M43925 M43721 B-63 3-65 INTERIM PROCEDURES FOR SHORT TERM BLACKcUT            08/27/81C g             {         ,_
SAFETY CONCERNS ASSOCIATED HITN PIPE BREAKS IN BHR     11/12/82C           (,    g g ., g*J,,,_ g         ql M46615     B-70         FATIGUE TRANSIENT LIMIT TS                            05/25/82C g
M51684     B-72        NUREG 0737 TECH SPECS (GENERIC LETTER 82-16)           03/19/84C N/A                tO M52773     B-76        ITEM 1.1 - POST TRIP REVIENs PROGRAM DESCRIPTION &     04/05/85C          {        Q 5-M                   ti M52854     B-77        ITEM 2.1 - EQUIPMENT CLASSIFICATION & VENDOR INTER
{        (},._ Q, g
           'M52935     B-78         IT' EMS 3.1.1 8 3.1.2 -POST MAINTENANCE TEST PROCEDU                                                              -
09/03/85C Q        pqg M53016 M54505 B-79         ITEM 3.1.3 - POST MAINTENANCE TESTING - CHANGES TO    09/03/85C q,      _
B-83        TECH SPECIFICATIONS COVERED BY GENERIC LETTERS 85-     12/15/85            --
q _ <g g M55602     B-84          INSPECTIONS OF BHR STAINLESS STEEL PIPING ACCORDIN   12/16/84C
 ,         .                                                                                                                                 (f6 l'

t R-1208731-001                   REGULATORY            INF0RMATION            TRACKING SYSTEM                     PAGE NO.      271
                                                                                                                                      ~
FA'CILITY        IMPLEMENTATION                                         03/31/86 MILLSTCNE 1                 (CONTINUATION)
LIC ACT                LICENSEE TAC NO. MPA 9                  TITLE                                 COMPLETE         STATUS        RAlf           ddfOY_
M53606     B-85 SALEM ATHS 1.2 DATA CAPABILITY                         02/15/86          [          6- Q'f - g6         N M53689     B-86 SALEM ATHS 2.2 5-R COMPONENTS                                             {        C{-th $               $
M53772     3-87 SALEM ATHS 3.2.1 8 3.2.2 S-R COMPONENTS                02/28/85C          {        3-g _ gjg              g M53855     B-88 SALEM ATHS 3.2.3 T.S. S-R COMPONENTS                   09/03/85C           Q       Lj,h_ rgg              g l   M54082     3-92 SALEM ATMS 4.5.1 DIVERSE TRIP FEATURES                 02/03/86C
{        Q _ Qj, g              ]g M53999     B-93 SALEM ATHS 4.5.2 8 4.5.3 TEST ALTERNATIVES                                Q         Lj - ('{ - g          y M08281     C-02                                                        08/20/79C BWR-RECIRC._ PUMP TRIP (ATHS)                                             {         Q g- Q                g M08060     C-10 CONTROL OF HEAVY LOADS OVER SPENT FUEL POOL (PHASE     07/19/84C
{         ] }Q. g               g M10910     C-11 RPS PONER SUPPLY                                       06/14/84C                                          y C-15 M52244          CONTROL OF HEAVY LOADS - PHASE II (FDLLONUP OF MPA     06/28/85C g
M07941     D-01 GE MARK I CONTAINMENT EVALUATION - LONG TERM M10069     D-11 FISSION GAS RELEASE 09/12/84C 10/t3/78C
{        $
M12290     D-15 HIGH ENERGY LINE BREAK 8 CONSEQUENTIAL SYSTEM FAIL     02/19/81C                                           ,
M43050     D-17 DEFINITION OF OPERABLE 05/23/84C           g         93_g M55876     D-19 DIESEL GENERATOR RELIABILITY TECH SPECS (GL 84-15)     09/06/85C
{         g _ y __ g M56741     D-20 MARK I DRYWELL VACUUM BREAKERS - LICENSEE RESPONSE     04/31/86                                              .
M44033     F-01 I.A.1.1      SHIFT TECHNICAL ADVISOR                   02/22/82C j
                                                                                               &       r 3     -M-M             g M44103     F-02 j                   I.A.1.3      SHIFT MANNING                             06/30/83C          Q         Q,g g                 g((       '
M44174     F-03              UPGRADING OF RO AND SRO TRAINING          01/07/83C I
I.A.2.1                                                                    C,       l 'l-Rh               G
   'M44245     F-04 I.D.1.2/3.A EMERGENCY OPERATING PROCEDURES GENERIC     03/26/85C            1      ]- Q M44315     F-05 I.C.1.2/3.5 PROCEDURES GENERATION PACKAGES (NUREG.                                 8'j . g @              g 06/15/86            1 M47228     F-06 I.C.5        FEEDBACK OF OPERATING EXPERIENCE          02/08/82C                    Q p 31 M47300     F-07 I.C.6        CORRECT PERFORMANCE OF OPERATING ACTIVITI 02/08/82C
{                              Q' Q       1.-$- g                gCg
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              ;.                                                                                                                                            c I
a R-1208731-001                    REGULAT0RY                     INF0RMATION             TRACKING     SYSTEM                    PAGE NO.      272 FACILITY                  IMPLEMENTATION                                          03/31/86 l     MILLSTONE 1              (CONTINUATION)
I LIC ACT                   LICENSEE bMk j       TAC NO. MPA 0                    TITLE                                            COMPLETE            STATUS         DATE
)       M51176    F-08 I.D 1.1 DETAILED CONTROL ROOM DESIGN REVIEW PROGRA                  07/10/87                       9; 0-M
                                                                                                                                                          ~
Cm M51254    F-89 I.D.2      SAFETY PARAMETER DISPLAY SYSTEM                          10/12/86
{            , gcg M44384    F-10 II.B.1     RCS HIGH POINT VENTS                                     06/27/83C Q         (3 ,gg , g         g           '
M47951    F-11 II.B.2     PLANT SHIELDING                                          06/07/83C                       q,g,
{
M44453    F-12 II.B.3     POST ACCIDENT SAMPLING                                   07/19/84C                      r}_ g(g, gt(
l                                                                                                                {
M44524    F-13 II.B.4     TRAINING FOR MITIGATING CORE DAMAGE                      01/07/83C                       \ _ q ._ {
{
M44594    F-14            RV AND SV TRAINING                                       03/14/83C
]
II.D.1
{       g,gg M44792    F-18 II.E.4.1         DEDICATED HYDROGEN PENETRATION                     08/12/81C
{        (g _ gg g g M44863    F-19 II.E.4.2         CONTAINMENT ISOLATION DEPENDA0!LITY                02/25/85C             1          p y __ y 9          q         l j       M64934    F-28 If_F.1.1         N00LE GAS MONITOR                                  11/23/81C             C        gg- A h- 3 {          Cfg M45005    F-21 II.F.1.2         IODINE / PARTICULATE SAMPLING                      11/23/81C l                                                                                                                 Q        ((_y- g (             g
!'      M45076    F-22 II.F.1.3         CONTAINMENT HIGN RANGE MONITOR                     84/15/82C Q        3 . C{- Q             ggg M47612    F-23 II.F.1.4         CONTAINMENT PRESSURE INSTRUMENT                    03/14/83C              L        3 Cg, %              gg i      M47683    F-24 II.F.1.5         CONTAINMENT HATER LEVEL INSTRUMENT                 03/14/83C              [         1 SD             [Of        ,
M47754    F-25 II.F.1.6         CONTAINMENT HYDROGEN MONITOR                       06/24/85C              &         3 -M- 8D            lDQ M45147    F-26 II.F.2           INSTRUMENTS FOR DETECTION ON INADEGUATE            03/26/85C               O_       3-MD-f$$            6
    . M57657      F-38 II.K.3.3         REPORTING SV AND RV FAILURES AND CHALLE            05/00/85C              O_        .6-1k-8$            1CD M45356    F-34 II.K.3.5         REPORTING SV AND RV FAILURES AND CHALLE            03/08/82C*             b        h-kQ                  [ O"")
M46530    F-43 II.K.3.13 NPCI AND RCIC INITIATION LEVELS                           04/14/82C               C.        3-Mb                10 3 M46531    F-44 If.K.3.14        ISOLATION CONDENSER ISOLATION MODIFICAT            09/15/81C               1       l1dC\- 3(             {Dk M46553    F-46 II.K.3.16        CHALLENGES AND FAILURES OF RELIEF VALVE            10/18/84C               [       Q-\l- M              llD M45642    F-47                                                                                                      Q-K -gd II.K.3.17        ECCS OUTAGES                                       08/10/83C                {                            gl}
M46534    F-48 II.K.3.18        ADS ACTUATION                                      03/14/83C
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s R-1288731-001                         REGULAT0RY           INF0RMATION             TRACKING         SYSTEM                        PAGE NO.        273 FACILITY        I.M P L E M E N T A T I O N                                         03/31/86 MILLSTONE 1                     (CONTINUATION)
LIC ACT                          LICENSEE                  ^
TAC NO,   MPA 8                        TITLE                                 COMPLETE                   STATUS        Mig              4 d f\l b M46535      F-49     II.K.3.19     INTERLOCK RECIRCULATION PUMP MODIFICATI   07/23/81C
{           gg                   gg3 M46536      F-50     II.K.3.21     RESTART OF CSS AND LPCI                   03/08/83C                                g,.g, g              gy
{
M48834      F-53     II.K.3.25 POWER ON PUMP SEALS                           11/18/82C
{           Ll K6              11 5 M46538      F-54     II.K.3.27     COMMON REFERENCE LEVEL                    12/11/8tC F-55
{          'g,           _
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                                                                                                                                                                ~
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{
M46539      F-56     II.K.3.29     PERFORMANCE OF ISOLATION CONDENSERS       09/15/81C                                (g , g ,g
{
! M45839          F-57     II.K.3.30     SS LOCA METHODS                           12/19/83C                                q _ g(g g
{                                g i M48178          F-58     II.K.3.31     COMPLIANCE HITH 10 CFR 50.46              12/19/83C                                Q g(g,g
{
M46540      F-59     II.K.3.44     ANTICIPATED TRANSIENTS HITH SINGLE FAIL   12/18/81C                     (.         Q.gg -g g              pg M46541      F-60                                                                                                      3_ g-gQ II.K.3.45     MANUAL DEPRESSURIZATION                   03/20/84C                     {                                   gg M45958      F-63     III.A.1.2 TECHNICAL SUPPORT CENTER                      11/12/86
{         qQg M46029      F-64     III.A.1.2     DPERATIONAL SUPPORT CENTER                02/10/87                                     _
M46101      F-65     III.A.1.2     EMERGENCY OPERATIONS FACILITY             02/10/87 M46173
{              q ,.
F-66     III.A.1.2     NUCLEAR DATA LINK                         07/30/82C                .
M46245      F-67     III.A.2.1     EMERGENCY PLAN UPGRADE TO MEET RULE       05/13/83C                                                                      -
M46317      F-68     III.A.2.2 E         5-&2                     m METEOROLOGICAL DATA UPGRADE               02/10/87
{ *, g g g g g g g g M46388      F-69     III.D.3.3     IMPLANT RADIATION MONITORING              07/07/81C
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1

a  .
Millstone Unit No. I Footnotes
: 1. NRC issued Amendment #64 to Licensee on 9/19/79. Amendrient #64 revised on 1/30/80. Replaced instrument inspection and testing technical specfication to meet 10CFR50.55a.
: 2. Closed.
: 3. RETS effective 1/1/86.         Our 4/22/86 letter to NRC:         Annual Environmental Operating Reports, Part B: Radiological, latest letter, Amendment #106.
4.
: 5. Amendment #51,7/6/78, closed.
: 6. Amendment #62,6/1/79, closed.
: 7. Amendment #62,6/1/79, closed.
8.
9.
10.
11.
12.
: 13. Incomplete. Most recent correspondence 3. F. Opeka letter to C. I. Grimes, dated 7/21/86 (B12123), "ISAP Topic No.1.18 - Anticipated Transients Without Scram."
14.
15.
16.
17.
: 18. Complete. W. G. Counsil letter to D. G. Eisenhut, dated 2/13/18, 

==Subject:==

          " Emergency Planning," submitted updated emergency plans.
i
: 19. -
20.
21.
22.
23.

Millstone Unit No. I Footnotes
: 24. Incomplete. 3. F. Opeka letter to C.1. Grimes, dated 7/3/86 (A05743 and B12139).
: 25. Incomplete. C.1. Grimes letter to 3. F. Opeka, dated 3/2/86, reduesting a modification to the purge / vent valves including automatic closure. By {{letter dated|date=July 3, 1986|text=letter dated July 3,1986}}, Millstone Unit No. I responded to the request for additional information. NRC is presently reviewing ~the submittal.
26.
: 27. D. C. Switzer letter to B. H. Grier, dated 3/2/78, " Response on December 22,1977 Adequately Resolved Concerns of Bulletin 78-03." No further response required.
: 28. D. L. Ziemann letter to W. G. Counsil, dated 11/30/78.
29.
: 30. R. W. Starostecki letter to W. G. Counsil, dated July 9,1982, Re: NRC Inspection Nos. 50-245/82-12 and 50-336/82-12. No violations observed.
: 31. D. L. Ziemann letter to W. G. Counsil, dated 9/26/78, Amendment 53.
32.
33.
: 34. - 45. NRC's 4/18/80 evlauation concluded that we met all Category "A"-
requirements.
46.
: 47. 3. M. Black memo to 3. F. Opeka, da'ted 1/21/80, i.e., Information Notice 79-37: Cracks in Keyway Areas - problem does not exist on GE turbine.
: 48. D. M. Crutchfield letter to W. G. Counsil, dated 9/11/80, re: ECCS clad swelling and rupture (Task No. B-47).
: 49. D. M. Crutchfield letter to W. G. Counsil, dated 4/19/83. Voltage analysis acceptable. Safety evaluation included.
: 50. D. G. Eisenhut letter to Licensees of All GE BWR Facilities, dated 6/15/81 (Generic Letter No. 81-24).
: 51. D. G. Eisenhut letter to All BWR Licensees, dated 1/23/81, (A01520) transmitting a generic SER. Reference (a) Order for Modification of License Concerning BWR Scram Discharge Systems, dated 1/9/81.
52.
: 53. Closed. 3. 3. Shea letter to 3. F. Opeka, dated 3/29/86, Safety Evaluation Report for Masonry Walt Design,IE Bulletin 80-11.

       .                .                                                                                                                                   Millstone Unit No. I Footnotes .
                    .54.
55.
: 56.           W. G. Counsil letter to B. H. Grier, dated 6/13/80 (A01060). 'Information satisfactory to resolve the concerns pertaining to the 3/13/80 Bulletin 80-06.
: 57.           D. M. Crutchfield letter to W. G. Counsil, dated 8/27/81. Implementation schedule acceptable.
58.
59.
: 60.          Not applicable. Applies only to PWRs.
61.
62.
i
: 63.          Closed. F. M. Akstulwicz letter to 3. F. Opeka, dated 2/21/86, 

==Subject:==

                                   " Post-Maintenance Testing and Reactor Trip System Reliability."
64.
65.
66.
: 67.           C. I. Grimes letter to 3. F. Opeka, dated 6/24/86 (A05865). Included an SER, closing this item, 68.
: 69.           See Footnote #63.                                                                                           l 70.
: 71.           See Footnote #63.
72.
73.
: 74.            Closed. W. A. Paulson letter to W. G. Counsil, dated 7/19/84, 

==Subject:==

                                   " Control of Heavy Loads (Phase I)."
75.
: 76.            Closed. H. L. Thompson letter to All Licensees, dated 6/28/85, closing Phase II of " Control of Heavy Loads" for all plants.
77.

    .i     .                                        -4 Millstone Unit No. I Footnotes 78.
79.
80.
: 81.      W. G. Counsil letter to D. G. Eisenhut, dated 2/4/85 (A04190),
                . transmitting information requested by Generic Letter 84-15.
8 2. .
: 83.      I.A.I.1, Letter dated 5/16/85, NU informs NRC of its continuous effort to -
Implement long-term STA plan.                            -
: 84. I.A.I.3, Amendment #108 dated 12/10/85. Response to application dated 7/9/85.-
: 85. I.A.2.1.4, D. M. Crutchfield letter to W. G. Counsil, dated 1/7/83. NRC contractor's review of our letters 8/15/80 and 5/10/82, concluded requirements met.
: 86.      1.C.I.2/3.A
: 87.      I.C.I.2/3.B, E. C. Wenzinger letter to 3. F. Opeka, dated 4/9/86. Letter states the symptomatic emergency operating procedures have been developed to conform with - the GE-BWR and CE-PWR Owner's Group Emergency Procedures Guidelines. No open items in this area. NRC asked questions about submittal, due to be resolved in July,1986.
: 88.      I.C.5, D. M. Crutchfield letter to W. G. Counsil, dated 2/8/82. Procedure acceptable; resolved.
: 89.      1.C.6, D. M. Crutchfield letter to W. G. CounsII, dated 2/8/82. Procedure acceptable; resolved.
: 90.      I.D.I.1, D. G. Eisenhut letter to All Boiling Water Reactor Licensees, Applicants for an Operating License. 

==Subject:==
NRC Staff review of the BWR Owner's Group (BWROG) control room survey program.
: 91.      I.D.2, E. C. Wenzinger letter to 3. F. Opeka, dated 9/12/85. Plant safety parameter display consoles not yet installed (1 & 2). Item open.
: 92.      II.B.1, Re #91. Closed.
i
;      93.       II.B.2, Re #91. Closed with Report 50-245/83-07.
t
: 94.       II.B.3,
;-     95.       II.B.4.1, R. A. Clark letter to W. G. Counsil, dated 1/7/83.        II.B.4.1 i
resolved (reviewed our submittals dated 8/15/80 and 5/10/82).
: 96.     'll.D.1, D. M. Crutchfield letter to W. G. Counsit, dated 12/16/83. Item i                resolved.
I

Millstone Unit No.1 Footnotes
: 97. II.E.4.1
: 98. II.E.4.2, C. I. Grimes letter to 3. F. Opeka, dated 5/2/86. Except for automatic closure of purge / vent valves on high drywell radiation signal, open items from February 25, 1985 safety evaluation are resolved.
Incorporated within ISAP.
: 99. II.F.I.1, R. A. Clark letter to W. G.'Counsil, dated 11/23/81. Information in our 10/16/82 letter resolved outstanding deviations.
100. II.F.1.2, See #99.
101. II.F.1.3, E. C. Wenzinger letter to 3. F. Opeka, dated 3/9/86. Item closed (II.F.1.3 - II.F.1.6).
102. II.F.1.4, E. C. Wenzinger letter to 3. F. Opeka, dated 3/9/86. Item closed.
103. II.F.1.5, See #102.
104. II.F.1.6, See #102.
105. II.F.2,3. A. Zwolinski letter to W. G. Counsil, dated 3/26/85. Closed.
106. II.K.3.3,3. A. Zwolinski letter to 3. F. Opeka, dated 5/22/85. Our {{letter dated|date=May 30, 1984|text=May 30, 1984 letter}} reviewed. O.K. to not incorporate additional reporting requirements into the technical specifications.
107. II.K.3.3, D. M. Crutchfield letter to W. G. Counsil, dated 3/8/82. Item resolved.
108. II.K.3.13, Utilizes a Feedwater Coolant Injection (FWCI) System and an Isolation Condener in lieu of HPCI/RCIC systems. Item is not applicable.
109. II.K.3.14, D. M. Crutchfield letter to W. G. Counsil, dated 12/29/81. Our response on 12/15/80 is acceptable. Open in terms of redundant monitor.
Have one, but the NRC wants another monitor installed. Projected completion date 12/31/86.
110. II.K.3.16, E. C. Wenzinger letter to 3. F. Opeka, dated 9/12/85. Re:
(NRC Regulation Report #50-245/85-22, 50-336/85-27) W. A. Paulson letter to      W. G. Counsif, dated 10/18/84, Serial #LS05-84-10-019.
Inspector to verify the procedural controls and technical specifications said to be in place. Item closed.
111. II.K.3.17 112. II.K.3.18, E. C. Wenzinger letter to 3. F. Opeka, dated 9/12/85. Closed (MP1 has isolation condenser.             No need for modification.) NRC Regulation 1 Report 50-245/85-22; 50-336/85-27.
113. II.K.3.19, March,1983, Docket No. 50-245, NUREG-0737, Item applies only to nonjet pump plants and is not applicable to Millstone Unit No.1.

Millstone Unit No. I Footnotes 114. II.K.3.21, D. M. Crutchfield letter to W. G. Coun'sil, dated 6/21/82. NRC agrees with the owner's group position that logic modifications for LPCI and low-pressure core spray are unwarranted.                     ;-
115. II.K.3.25 116. ~ II.K.3.27 117. II.K.3.28 118. II.K.3.29 119. II.K.3.30, D. M. Crutchfield letter to W. G. Counsil, dated 12/19/83.
Action item complete.
120. II.K.3.31, D. M. Crutchfield letter to W. G. Counsil, dated 12/19/83.
Action item complete.
121. II.K.3.44, D. M. Crutchfield letter to W. G. Counsil, dated 12/18/81. Item complete.
122. II.K.3.45, D. M. Crutchfield letter to W. G. Counsil, dated 3/20/84.
             " Alternative modes of depressurization would not contribute to plant safety, no modification to MP1 plant design or operation is required."
123. III.A.I.2, E. C. Wenzinger letter to ,3. F. Opeka, dated 4/9/86. TSC completed with MP3. Demonstrated to be operational. Item closed.
124. Ill.A.I.2 125. III.A.I.2, D. G. Eisenhut letter to W. G. Counsil, dated 6/7/84. Alternate location (i.e., Corporate Emergency Operations Facility in Berlin) is acceptable.
126. III.A.I.2, No action required.
127. III.A.2.1, D. M. Crutchfield letter to W. G. Counsil, dated 5/13/83. Item complete.
I 128. III.A.2.2, Docket #50-245, Attachment 2, Generic Letter 82-10, "We believe that this specific TMI action item should be deferred and should be addressed in concert with our implementation of the fundamental NRC requirements for emergency response capability." Superceded by Generic Letter 82-33.
129. Ill.D.3.3, D. M. Crutchfield letter to W. G. Counsil, dated 6/29/82. No further review planned, i.e., if we meet the position to improve in-plant lodine instrumentation. W. G. Counsil response to D. M. Crutchfield, dated 7/20/82. CYAPCO and NNECO fully meet the position and no deviations are requested.

            ,     ,                                                  7_
Millstone Unit No. I Footnotes 130.          III.D.3.4, J. A. Zwolinski letter to J. F. Opeka, dated 7/1/85.
Amendment #103 issued to provisional operating License DPR-21 (change to completion date).
131.          I.D.I.2, D.-G. Eisenhut letter to all BWR Licensees, dated 4/19/83. On-going improvement process, additional work required. (January 1989) 1 1
i

i REOULAT0RY         INF0RMATION                             TRACKINO       $Y$ TEM                            PAGE NO.8       ZII
]R-1288731-est l                                                               FACILITY                    IMPLEMENTATION                                                                  03731/3 L
l:ACILITY MILLSTONE 2
!'LANTLOCATION: 5 MI SH OF NEN LONDON, CONN                          LICENSED POWER: 2700 MNT                               PROJECT MANAGER: D. OSBORNE i3OCKET NUMBER: 850-80334                                            DESIGN POWER:             8878 004E '                  SRANCH CHIEF:             A. THADANI
;tRCH/ ENGINEER: BECH                                                NSSS VENDOR:              COMB                         LIC. ASSISTANT: P. KREUTZER JE ICSPECTOR:         T. SNEDLOSKY LIC ACT                              LICENSEE
,?AC NO. MPA 8                                    TITLE                                         COMPLETE                       1IAIjg              jgg 108320      A-01                                                                                  11/04/42C 10 CFR 58.55 A(G) - ISI
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l 111391                                                                                                                                       g jg ,g                   y            l 110560      A-10           CONTINGENCY PLANNING                                                   04/05/83C
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{      3 \0 21                      b VITAL AREA ANALYSIS                                                    84/14/82C
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{ Q gq ]g                           g PHR MODERATOR DILUTION                                                  03/01/79C Q     p g _]Q                       g
' 106749      B-04          REACTOR VESSEL OVERPRESSURE PROTECTION                                  83/23/79C 187544      3-07
{      3,,,,g,,,,                     g STEAM GENERATOR FEEDHATER FLOW INSTABILITY                              85/87/80C 184169      B-04          PWR NPSI-LPSI FLON RESISTANCE                                           12/88/74C E     5 q-@                          A    ~
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 ,       -1208731-001               REOULAT0RY                        INF0RMATION                TRACKINO     5YSTEM                                       PA!E NO       2 FACILITY                     IMPLEMENTATION                                                                     0}/31/:
}        ILLSTONE 2            (CONTINUATION)
LIC ACT                                 LICENSEE IAC No. MPA_0               TITLE                                            COMPLETE                    STATUS               MIE                 [M 07846    B-09 CHARGING SYSTEMS PIPE VIBRATIONS                               11/09/78C                                  g     Q, g 07220    3-14 CEA GUIDE TURE WEAR                                            06/29/81C                     g               ,, y ,_ g 12983    B-16 EMERGENCY PLANNING AND REVISIONS                               01/01/70C C            #2 fo                    2.3 08959    B-17 TECH SPEC SURVEILLANCE FOR HYDRAULIC SNUBBERS                  08/02/84C
{                  Q,g                       y 06546    B-19 NEUTRON SHIELDING - CE REACTORS                                05/12/79C                                      ,f_ f ;t _79 ~
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* I j                                                        FACILITY       IMPLEMENTATION                                       05/31,
!     ILLSTONE 2                 (CONTINUATION) 1 LIC ACT               LICENSEE 1     AC NO. MPA 0                  TITLE                                   COMPLETE        STATUS        jl&IE 30197     B-44    LESSONS LEARNED IMPLEMENTATION                        03/26/80C
(         Q-16.$Q          44 30198     B-44    LESSONS LEARNED IMPLEMENTATION                        03/26/80C                  g.ggg             y6 l                                                                                              {
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LIC ACT                       LICENSEE 1       AC No. MPA 0                   TITLE                                COMPLETE               STATUS          MIE 43926     B-63   INTERIM PRGCEDURES FOR SHORT TERM BLACKOUT           88/27/81C
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       - 208731-001                                                QEOULATORY            INF0RMATION               TRACKINO  $YSTEM                        PAGE NO.s FACILITY        IMPLEM.ENTATION                                                 43/3.
ILLSTONE 2                                             (CONTINUATION)
LIC ACT                  LICENSEE AC NO.       MPA 0                                           TITLE                                    COMPLETE          STATUS          DAI.E       IMk
    '08061           C-10 CONTROL OF HEAVY LOADS OVER SPENT FUEL POOL (PHASE        09/14/84C          {           Q-j@g            g 110464           C-12                          BORON SOLUBILITY DURING LONG TERM COOLING FOLLONIN        06/29/81C          L          b- $_M            Q)
M3656
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1158070           C-16
   .408949           D-10 UTILITY RESPONSES TO STAFF RECOMMENDATIONS CONCERN ASYMMETRIC LOCA LOADS 12/30/85            C           l -a 4-y(,       %l         i
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11/19/80C           [         \\-\Q-gQ           Q{
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            -1203731-001                     REOULAT0RY             INFGRMATICN          TRACKINO SYSTEM                 PAGE NO.8 FACILITY         IMPLEMENTATION                      ,             g3/3
           .ILLSTONE 2                  (CONTINUATION)                                                                          -
LIC ACT              LICENSEE AC NO. MPA 8                    TITLE                                 COMPLETE        STATUS      DAIE            2 47952     F-11  II.B.2       PLANT SHIELDING                            05/24/83C        b        h-Q.86       lO 44454     F-12  II.B.3       POST ACCIDENT SAMPLING                     06/14/84C        [        h-\Q-gQ      llQ 44525      F-13 l                           II.B.4       TRAINING FOR MITIGATING CORE DAMAGE        01/07/83C        {         {-q-83      ll6 44595      F-14 I I . D.1    RV AND SV TRAINING                         05/15/86         I         h -ll- $$    ll(p_l 44665      F-15  II.E.1.1 AFM SYSTEM EVALUATIGN                          01/14/81C                 Q-g gl
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{       h_,gg,g        lg F-18  II.E.4.1       DEDICATED NYDROGEN PENETRATION           09/18/81C Q        Q-gg,gj        y 144864      F-19  II.E.4.2       CONTAINMENT ISOLATION DEPENDABILITY      O2/28/86C
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     -1208731-001                    REOULAT0RY            INF0RMATION            TRACKINO   SYSTEM                     PAGE NO.8 FACILITY          IMPLEMENTATION                                              (F3 ILLSTONE 2                  (CONTINUATION)                                                                                   -
LIC ACT                 LICENSEE AC NO. MPA 0                  TITLE                                  COMPLETE          STATUS       DAIE         __ __
   '43447        F-53 II.K.3.25     POWER ON PUMP SEALS                      04/05/83C
[        QpQ                  g
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05/01/86            [                             lg 18179       F-58 II.K.3.31     COMPLIANCE HITN 10 CFR 50.46             07/31/87            L        b.gg_g$              jg
     %5959       F-63 III.A.1.2     TECHNICAL SUPPORT CENTER                 06/31/87                     y-$$                 lp f_
     %6030       F-64 III.A.1.2 OPERATIONAL SUPPORT CENTER                                        C.       F-11-T4             140 l 46102        F-65                                                        06/07/84C                    hqg III.A.1.2     EMERGENCY OPERATIONS FACILITY
{                             lyl 46174        F-66 III.A.1.2     NUCLEAR DATA LINK                        07/30/82C                      y/A                fyL l 46246        F-67 III.A.2.1     EMERGENCY PLAN UPGRADE TO MEET RULE      05/13/83C F-68 E        5-B-83               N3 46318 46389        F-69 III.A.2.2 METEOROLOGICAL DATA UPGRADE III.D.3.3     IMPLANT RADIATION MONITORING 06/31/87
( ggg g Q g g fg 06/29/82C        { pgg g.g g jg 46458        F-70 III.D.3.4     CONTROL ROOM HABITABILITY               ~07/19/82C~          7        4-l.-37              lyg l 156139       F-71 I.D.1.2 DETAILED CONTROL ROOM REVIEN (FDLLONUP TO      12/30/86             T_       q _ g 6 - T (,      lL.[-~f l
  .149658        G-01 REACTOR COOLANT PUMP TRIP (D660 - II.K.3.5)            01/31/86 7       g,gl _ g                     l
: r.  .
Millstone Unit No. 2 Footnotes
: 1. 3. F. Opeka letter to S. D. Ebneter, dated 4/7/86 (Bil882)
: 2. Closed, B ill86, RETS effective.           Our 4/22/86 letter:      Annual Environmental Operating Reports, Part B.
: 3. D. L. Ziemann letter to W. G. Counsil, dated 2/23/,79, Amendment #48.
: 4. Closed by internal NRC memorandum, dated 3/18/86.
l
: 5. Closed, R. A. Clark letter to W. G. Counsil, dated April 5,1983,           l Amendment #84.
: 6. Closed,. R. A. Clark letter to W. G. Counsil, dated March 10, 1982, Amendment #75.
: 7. Combined Inspection 50-245/82-03 and 50-336/82-05 (A02430), dated 4/4/82. Physical barriers and detection aids - no violations noted.
: 8. 3. F. Opeka letter to S. D. Ebneter, dated 4/7/86 (Bil882).
: 9. E. L. Conner telecommunication with M. P. Cass on 4/11/80. Mr. Cass told Mr. Conner that diesel fuel oil is in QA program. . Mr. Conner said this verbal response was acceptable.
: 10. 11/17/81 acceptance of our response to Generic Letter 81-01 (A02121).
: 11. Incomplete NRC order from 3. F. Butcher to 3. F. Opeka, dated 7/27/85.
: 12. 3. F. Opeka letter to 3. A. Zwolinski dated 7/9/86, responding to Generic Letter 83-43, and proposing revisions to tech, specs.; awaiting response from NRC Staff.
: 13. Incomplete. 3. F. Opeka letter to C. I. Grimes, dated 2/18/86. Complete by 6/25/86 - ISAP review. To submit exemption request . by 7/29/86.
(A05442) 14,   3. F. Opeka letter to C. I. Grimes, dated 1/23/86. (B11972)
: 15. R. W. Reid letter to W. G.' Counsil, dated 9/19/78, Amendment #43.
: 16. See #15.
: 17. R. W. Reid letter to W. G. Counsil, dated 3/1/79.
: 18. Complete 3/23/79, Amendment #50. (A00374)
: 19. R. W. Reid letter to W. G. Counsil, dated 5/7/80, Amendment #56.
I    20. R. W. Reid letter to W. G. Counsil, dated 12/8/78, Amendment #45.
(A00246)
: 21. Item closed by R. W. Reid letter to W. G. Counsil, dated 11/9/78.

y d b Millstone Unit No. 2 Footnotes
: 22. R. A. Clark letter to W. G. Counsil, dated 6/29/81. "...we believe it is time to accept the sleeving of guide tubes as a solution to the wear problems."
: 23. W. G. Counsil letter to D. G. Eisenhut, dated 12/31/80, 

==Subject:==

Emergency Planning.
     -24. D. B. Osborne letter to W. G. Couns'il, dated 8/2/84, Amendment #96.
(A04239)
: 25. R. W. Reid letter to W. G. Counsil, dated May 12,1979, Amendment #52.
: 26. N/A
: 27. Closed by internal NRC memorandum, dated 2/23/82.
: 28. D. B. Osborne letter to W. G. Counsil, dated 8/2/84, Amendment #96.
: 29. E. 3. Butcher letter to 3. F. Opeka, dated 10/28/85.
l
: 30. R. A. Clark letter to W. G. Counsil, dated 10/6/80, Amendment #61.
: 31. N/A
: 32. Complete, (A03992) 3. R. Miller letter to W. G. Counsil, dated 5/15/84, Completion of Issues Concering Containment Venting and Purging.
: 33. Closed by internal NRC memorandum, dated 8/18/86.                          i
: 34. Complete, (A01819) Clark letter to W. G. Counsil, dated 12/27/84, Request for Technical Specification Change on RTDs.
: 35. R. W. Reid letter to D. C. Switzer, dated 4/14/78, Amemdment #37.
: 36. R. A. Clark letter to W. G. Counsil, dated 10/6/80, Amendment #61.
: 37. Closed by internal NRC memoranc'um, dated 11/13/30.
l
: 38. Update: 3. F. Opeka letter to Grimes /Thadani/Noonan, dated 5/30/86.
Proposed changes to Technical Specifications, Fire Protection Audits.
: 39. R. A. Clark letter to W. G. Counsit, dated 10/21/80, Safety Evt.luation of Additional items.
: 40. R. A. Clark letter to W. G. Counsil, dated 4/7/81, Amemdment #66.            l
: 41. Complete, (A00928) Reid letter to W. G. Counsil, dated 3/13/80, SER on Feedwater Piping.
: 42. Closed by internal NRC memorandum, dated 4/4/80.
43 - 57. Complete. R. W. Reid letter to W. G. Cousil, dated 2/25/80.

e    a
                                                    .                                       Millstone Unit No. 2 Footnotes
: 58.      R. A. Clark letter to W. G. Counsil,' dated 8/15/80.
: 59. See Footnota 40.
l J 60. Complete, Clark letter to W. G. Counsil, dated 8/31/81, NRC to Discontinue Stress Corrosion Cracking. (A01950)
: 61. Complete, Clark letter to W. . G. Counsil, dated 9/10/80.            (A01298)
Acknowledgement of response on ECCS.
: 62. - Complete, D. M.' Crutchfield letter to W. G. Counsil, dated 4/19/83, NRC
               - Review and Acceptance of NNECO's Report on Adequacy of Station Electric Distribution System Voltages. Response letter dated 6/24/83. .
(A03197)
: 63. Complete, 3. R. Miller letter to W. G. Counsil, dated 4/17/85, NRC .
review of NNECO's Response to IE Bulletin 80-11, Masonry Wall Design.
Response letter dated 3/22/85. (A04832)
: 64. Complete, dated 7/4/85. (W. G. Counsit to D. G. Eisnehut dated 2/85...to -
be done during outage.)
: 65. Closed by internal NRC memorandum from M. B. Fairtile to all ORPMs, dated 7/28/82, subject: "Close-Out of MPA 61 - NRR Portion of Review of IE Bulletin 79-27."
: 66. Closed .via Internal NRC memorandum from the Staff to I&E, dated l
               '6/10/82.
: 67. W. G. Counsil letter to D. G. Eisenhut, dated 6/4/81. (A01473) Complete, D. M. Crutchfield letter to W. G. Counsil, dated 8/27/81. Implementation schedule acceptable.
: 68. Closed, W. G. Counsil letter to D. G. Eisenhut, dated 11/19/81, " Natural Circulation Cooldown."
69.-    Closed, Clark letter to W. G. Counsil, dated 10/7/82, Submittal on
                " Resolution of Main Steam Line Break with Continued Feedwater Addition Event." (A02817)
: 70. Closed by internal NRC memorandum, dated 5/27/82.
l l       71. W.~ G. Counsil letter to D. G. Eisenhut, dated 12/30/80. (B10637)
: 72. Closed by internal NRC memorandum, dated 4/12/84.
l
: 73. Complete, E. 3. Butcher letter to 3. F. Opel<a, dated 7/10/85, " Post-Trip
              . Review and Procedure."                                                           l
       '74.-    Closed. 3. F. Opeka letter to 3. A. Zwolinski, dated 5/9/85. (A04826) l
: 75. Complete, A. C. Thadani letter to 3. F. Opeka, dated 3/18/86, " Response
,               to Generic Letter 83-28, Items 3.1.1, 3.1.2, 3.2.1, 3.2.2, 4.1, and 4.5.1."
l l_ .

e so Millstone Unit No. 2 Footnotes
: 76. Complete, E. 3. Butcher let'ter to 3. F. Opeka, dated 10/24/85, " Response to Generic Letter 83-28, Items 3.1.3 and 3.2.3."
77.' See Footnote #75.
   ~78. Closed. 3. F. Opeka letter to A. C. Thadini, dated 4/10/86. (B12057)
: 79. Currently processing license amendment request to provide technical specifications for this item.
: 80. Closed. 3. F. Opeka letter to A. C. Thadini, dated 1/10/86. (A05364)
: 81. Closed. 3. F. Opeka letter to 3. A. Zwolinski, dated 5/9/85. (A04826)
: 32. See Footnote #75.
l
: 83. See Footnote #76.
                                                                                    .g
: 84. Not completed yet.
: 85. See Footnote #75.
l
: 86.  (4.5.2) Not applicable - on-line functional testing is performed.
(4.5.3) Closed. 3. F. Opeka letter to E. 3. Butcher, dated 11/21/85.
(A04826)
: 87. Not complete yet. On-going negotiations between the NRC Staff and NNECO.
: 88. Closed by internal NRC memorandum, dated 8/18/86.                            l
: 89. R. W. Reid letter to W. G. Counsit, dated May. 12,1979, Amendment #52.
: 90. Closed,3. R. Miller letter to W. G. Counsil, dated 9/14/84," Resolution of l Control of Heavy Loads (Phase 1)."
: 91. Closed, Clark letter to W. G. Counsil, dated 6/29/81, Staff Review of Long-Term Cooling Submittals. (A01820)
: 92. Closed, Clark letter to W. G. Counsil,' dated 9/30/82, Resolution of the Seismic Qualification of Auxiliary Feedwater System. (A02795)
: 93. Closed by NRC Generic Letter 85-11, dated June 28,1985.                      l
: 94. Closed by internal NRC memorandum, dated 1/22/86.                            l
: 95. Not complete yet. Pending action on the part of the NRC Staff.
: 96. R. W. Reid letter to W. G. Counsil, dated May 12,1979, Amendment #52.
: 97. Closed by internal NRC memorandum, dated 2/2/84.
: 98. T. M. Novak/G. C. Lainas letter to W. G. Counsil, dated 11/19/80, Amendment #62.

.e 4   -
Millstone Unit No. 2 Footnotes
: 99. W. G. Counsil letter to D. G. Eisenhut, dated 2/5/85.
requested by Generic Letter 84-15.                               Information l 100. R. A. Clark letter to W. G. Counsil, dated October 6,1980, Amendment
            #61.
101. Closed, dated 4/23/82. Response letter dated 10/22/82. (A02456) 102. Closed, dated 3/31/82. Response letter dated 6/25/84. (A02399) 103. I.A.l.1, Letter dated 5/16/85, NU informs NRC of its continuous effort to implement long-term STA plan.
104. I.A.I.3, Amendment #106 dated 12/10/85. Response to application dated 7/9/85.
105. I.A.2.1.4, D. M. Crutchfield letter to W. G. Counsil, dated 1/7/83. NRC contractor's review of our letters 8/15/80 and 5/10/82, concluded requirements met.
106. I.C.I.2/3.A, Closed by internal NRC memorandum, dated 6/7/84.                 l 107. 1.C.I.2/3.B, E. C. Wenzinger letter to 3. F. Opeka, dated 4/9/86. Letter states the symptomatic emergency operating procedures have been developed to conform with the GE-BWR and CE-PWR Owner's Group Emergency Procedures Guidelines. No open items in this area. NRC asked questions about submittal, due to be resolved in 1986.
108.  .I.C.5, D. M. Crutchfield letter to W.- G. Counsil, dated 2/8/82. Procedure acceptable; resolved.
109. 1.C.6, D. M. Crutchfield letter to W. G. Counsil, dated 2/8/82. Procedure acceptable; resolved.
110.
1.D.I.1, CRDR program plan is scheduled for submittal to the NRC Staff l on 9/26/86.
111. 1.D.2, E. C. Wenzinger letter to 3. F. Opeka, dated 9/12/85. Plant safety parameter display consoles not yet installed (1 & 2). Item open. SPDS is to be fully operational by 3/27/87 or by start-up for Cycle 8, whichever is later, based on a confirmatory order, dated 7/27/85.
112. II.B.1,3. R. Miller letter to W. G. Counsil, dated 9/20/83. Issue resolved. l 113. II.B.2, Reference #111. Closed with with PDCR 2-132-82 in Inspection Report 83-09. NRC Region I Report 50-245/85-2;!; 50-336/85-27.
114. II.B.3,3. R. Miller letter to W. G. Counsil, dated 6/14/84. Issue resolved.
l 115. II.B.4.1, R. A. Clark letter to W. G. Counsil, dated 1/7/83.          II.B.4.1 resolved (reviewed our submittals dated 8/15/80 and 5/10/82).
116. II.D.1, 3. F. Opeka letter to E. 3. Butcher, dated 6/11/85. Response sent, NRC review pending.                                                            l

oss Millstone Unit No. 2 Footnotes 117. II.E.1.1, R. A. Clark letter to W. G. Counsil, dated 9/30/82. Issue resolved (our letters of 7/24/81 and 6/4/82).
118. II.E.1.2.1, R. A. Clark letter to W. G. Counsil, dated 6/18/82. Item closed (except for recommended technical specification changes).
 -119. II.E.1.2.2, R. A. Clark letter to W. G. Counsil, dated 6/18/82. Item closed (except for the recommended technical specification changes).
120. II.E.4.1, R. A. Clark letter to W. G. Counsi!, dated 9/18/81.           Item resolved.
121. II.E.4.2, D. B. Osborne letter to 3. F. Opeka, dated 2/28/86.
  .122. II.F.1.1, R. A. Clark letter to W. G. Counsil, dated 11/23/81. Information in our 10/16/82 letter resolved outstanding deviations.
I23. II.F.1.2, See # 122.
124. II.F.1.3, E. C. Wenzinger letter to 3. F. Opeka, dated 3/9/86. Item closed (ll.F.1.3 - II.F.1.6). 4/9/86 Inspection 50-245/85-26; 50-336/85-32 125. II.F.1.4, R. A. Clark letter to W. G. Counsil, dated 6/27/83.
I26. II.F.1.5, See # 125.
 -127. II.F.1.6, See # 125.
128. II.F.2, D. H. Jaffe letter to 3. F. Opeka, dated 8/28/86, " Safety Evaluation Issue."
129. II.K.2.13, 3. R. Miller letter to W. G. Counsil, dated 6/11/84. Item complete.
130. II.K .2.17,   3. R. Miller letter to W. G. Counsil, dated 10/21/83.
Requirements met. Review completed.
131. II.K.3.1, Closed decision in 3. R. Miller letter to W. G. Counsil, dated 9/23/83 (no serial #).
132. II.K .3.2,   3. R. Miller letter to     W. G. Counsil, dated 9/23/83.
Requirements met with existing PORV.
133. II.K.3.3, D. M. Crutchfield letter to W. G. Counsil, dated 3/8/82. Item resolved.
134. II.K.3.5, H. L. Thompson letter to All Applicants and Licensees with Westinghouse Designed NSSSs, dated 6/28/85. Generic Letter 86-06 has been issued; NNECO committed to a 10/31/86 response date.
135. II.K .3.17,   R. A. Clark letter to          W. G. Counsil, dated 8/8/83.
Requirements met.
136. II.K.3.25, R. A. Clark letter to W. G. Counsil, dated 4/5/83. Resolved.

c P ' 4 ''d Millstone Unit No. 2 Footnotes 137. II.K.3.30, C. D. Thomas letter to R. W. Wells, dated 6/20/85. According to page 13 of the safety evaluation report, the Staff finds II.K.3.30 resolved for C.E. plants. (Continues to II.K.3.31 for MP2.)
138. II.K.3.31, C. D. Thomas letter to R. W. Wells, dated 6/20/85. Page 13 of safety evaluation: "With an acceptable calculation / data comparison, the requirements to perform plant specification analysis, per II.K.3.31, will no longer be required."
139. III.A.I.2, E. C. Wenzinger letter to 3. F. Opeka, dated 4/9/86. TSC completed with MP3. Demonstrated to be operational. Item closed.
140. III.A.I.2, the O.S.C. was placed into operation with procedures on 5/21/84.
141. III.A.I.2, D. G. Eisenhut letter to W. G. Counsil, dated 6/7/84. Alternate location (i.e., Corporate Emergency Operations Facility in Berlin) is acceptable.
142. Ill.A.I.2, The item was designated as N/A based on an mternal NRC memorandum, dated 8/18/86.
143. III.A.2.1, D. M. Crutchfield letter to W. G. Counsil, dated 5/13/83. Item complete.
144. Ill.A.2.2, Docket /!50-245, Attachment 2, Generic Letter 82-10,. "We believe that this specific TMI action item should be deferred and should be addressed in concert with our implementation of the fundamental NRC requirements for emergency response capability." Superceded by Generic Letter 82-33.
145. Ill.D.3.3, D. M. Crutchfield letter to W. G. Counsil, dated 6/29/82. No further review planned, i.e., if we meet the position to improve in-plant iodine instrumentation. W. G. Counsil response to D. M. Crutchfield, dated 7/20/82: CYAPCO and NNECO fully meet the position and no deviations are requested.
146. III.D.3.4, Not completc yet. NRC Staff is working with NNECO on this.
l 147. I.D.I.2, CRDR Summary Report is scheduled for transmittal to the NRC Staff on 9/26/86.
148. II.K.3.5, Reactor Coolant Pump Trip. Generic Letter 86-06 was issued by the NRC Staff; NNECO has committed to respond by 10/31/86.
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