ML20137R106

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Twenty-fourth Partial Response to FOIA Request for Documents.Forwards Documents Listed in App Ddd.Documents Being Released in Entirety.Copyright Documents Withheld
ML20137R106
Person / Time
Site: Saint Lucie, North Anna, Turkey Point  NextEra Energy icon.png
Issue date: 04/04/1997
From: Racquel Powell
NRC OFFICE OF ADMINISTRATION (ADM)
To: Binder N
DEBEVOISE & PLIMPTON
Shared Package
ML20137R112 List:
References
FOIA-96-485 NUDOCS 9704140043
Download: ML20137R106 (12)


Text

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RESPONSE TYPE 6 RESPONSE TC FREEOOM OF I FINAL { X l PARTIAL (24tn)

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INFORMATION ACT (FOIA) REQUEST 4 see ..

W R 0 4 1997 DOCKET NUMBER ($1(if apphcable) 1EOUESTEa Neil S. Binder, PART l - AGENCY RECORDS RELE ASED OR NOT LOCATED (See checAedboxes)

N3 agency records subject to the request have been located.

Na additional agency records subject to the request have been located.

Requested records are available through another public distribution program. See Comments section,

    • 'ancy records subject to the request that are identified in Appendix (es) are already available for public inspection and copying at the N ov. Alic Document Room,2120 L Street, N.W., Washington, DC.

A, records subject to the request that are identified in Appendix (es) D00 are being made available for public inspection and copying

.g et in. NRC Public Document Room,2120 L Street, N.W., Washington, DC, in a folder under this FOl A number.

The nonproprietary version of the proposal (s) that you agreed to accept in a telephone conversation with a member of my staff is now being made available for public inspection and copying at the N RC Public Document Room,2120 L Street, N.W., Washington, DC, in a folder under this FOI A number.

Agerwy records subject to the request that a.e Identified in Appendix (es) may be inspected and copied at the N RC Local Public Document Room identified in the Comments section.

Enclosed is information on how you may obtain access to and the charges for copying records located at the NR7 Public Document Room,2120 L Street, Nr!., Washington, DC.

X Agency records subject to the request are enclosed.

  • i

! Records subject to the request have been referred to another Federal agency (ies) for review and direct response to you.

Foss You will be billed by the N RC for fees totaling s You will teceive a refund from the NRC in the amount of s ,

in view of N RC's response to this request, no further action is being ;aken on appeal letter dated . No.

PART 11. A-lNFORMATION WITHHELD FROM PUBLIC DISCLOSURE C:rtijn information in the requested records is being withheld from public disclosure pursuant to the exemptions described in and for the reasons stated in Pcrt 11, B, C, and D, Any released portions of the documents for which only part of the record is being withheld are being made available for public Jnspection and copying in the NRC Public Document Room,2120 L Street, N.W., Washington, DC in a folder under this FOI A number.

COMMEhTS

  • Copies of the records identified on Appendix DDD. are enclosed, with the exception of

' documents 82 and 93 which are copyrighted. These records are available for inspection only at the NRC's Public Document Room.

D l 9704140043 970404 PDR FOIA PDR 1 .

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BINDER 96-485

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3 RECORDS:BEING RELEASED IN THEIR ENTIRETY-(IF COPYRIGHTED IDENTIFY WITH *)  !

NO. - DATE ' DESCRIPTION /(PAGE COUNT) I

1. 03/07/96 St. Lucie Enforcement Conference Overdilution Event (14 pages) -

2 Undated FP&L St. Lucie Plant Unit No. 1 Facility Operating License, j Updated per Amendment 134 dated 03/15/95 (4 pages) l

3. Undated St. Lucie Unit l'FSAR (2 pages)  !
4. Undated' FP&L St. Lucie Plant Administrative Procedure No. 0010120. .

1 T- Revision 79 (17 pages)  ;

5. ,12/00/95 FP&L Nuclear Energy Department. St. Lucie Plant.

Preparation. Revision. Review / Approval of Procedures  !

(4 pages)  !

p 6. Undated FP&L St. Lucie Unit-1. Operating Procedure No. 1-0250020 l

' Revision 35 (15 pages) r

7. 03/28/96 Letter from A. F Gibson to G. H. Holzmacher.

Subject:

NRC i a

Inspection Report No. 50-335/96-03 and 50-389/96-03 l (4 pages)

8. Undated Pages from inspection report (2 pages)
9. 03/29/96 Press Release.

Subject:

NRC Staff Proposed $50.000 Civil Penalty Against St Lucie Nuclear Power Plant

10. 03/25/96 ' Office of Enforcement Notification of Significant Enforcement Action. EN 96-020 (4 pages)

.11. 03/28/96 Letter from Stewart D. Ebneter to FP&L.

Subject:

Notice of Violation and Proposed Imposition of Civil Penalty -

$50.000 (NRC Inspection Report No. 50-33S/96-03 and 50-

'389/96-03) (11 pages) 12.- 03/28/96 Letter.to FF&L.

Subject:

Notice of Violation and Proposed Imposition of Civil Penalty - $50,000 (NRC Inspection Report No. 50-335/96-03 and 50-389/96-03) (1 page) 13.- 03/29/96 Press Release.

Subject:

NRC Staff Proposes $50.000 Civil Penalty Against St. Lucie Nuclear Power Plant (2 pages)

.F 4

J

t -

Re: FOIA-96-485 NO. DATE DESCRIPTION /(PAGE COUNT)

14. 04/23/96 Letter from T. F. Plunkett to James Lieberman.

Subject:

St. Lucie Unit 1. Docket No. 50-335. Inspection Report 96-03, Reply to Notice of Violation EA 96-040 (9 pages)

15. 02/22/96 Letter from A. F. Gibson to FP&L.

Subject:

NRC Inspection Report Nos. 50-335/96-03 and 50-389/96-03 (34 Pages)

16. 03/06/96 Letter from W. H. Bohlke to USNRC.

Subject:

St. Lucie Units 1 and 2. Docket Nos. 50-335 and 50-389. Excess Dilution of the Reactor Coolant System Due to Personnel Error. Nuclear Problem Report 96-008, Revision 1 (13 pages)

17. Undated 10 CFR 50.59 Safety Evaluation for Chemical and Volume Control System Operation (20 pages)
18. 03/13/96 Letter from Charles A. Casto to FP&L.

Subject:

Meeting Summary - Predecisiorial Enforcement Conference. St. Lucie -

Docket Nos. 50-335 and 50-389 (22 pages)

19. Undated Handwritten notes (7 pages) ,
20. 03/08/96 Pre-decisional Enforcement Conference. St. Lucie Plant. NRC l Inspection Report Nos. 50-335/96-03 and 50-389/96-03 l (20 pages)
21. Undated Label. ENO. 95E035. EA: 95-222 (1 page).
22. 11/14/95 NRC Pre-decisional Enforcement Conference (31 pages)
23. Undated Handwritten notes (3 pages)
24. 11/28/95 Letter from Ellis W. Merschoff to FP&L.

Subject:

Notice of Violation (NRC Inspection Report Nos. 50-335/95-20 and 50-389/95-20) (42 pages)

25. 12/06/95 Letter from J. H. Golberg to James Lieberman.

Subject:

St. Lucie Unit 1. Docket No. 50-335. Inspection Report l 95-16. Reply to Notice of Violation EA 95-180 (9 pages) l

26. 10/24/96 Letter from Kerry D. Landis to FP&L.

Subject:

Closed Meeting Announcement - Predecisional Enforcement Conference. St. Lucie - Docket No. 50-335, 389 (3 pages)

27. 10/26/95 Letter from Ellis W. Merschoff to FP&L,

Subject:

NRC Inspection Report Nos. 50-335/95-20 and 50-389/95-20 (14 pages) i I

l l

I

v -

.Re: F01A-96-485 ,

NO. DATE DESCP,IPTION/(PAGE COUNT)

28. 12/19/95 Letter from J. H. Goldberg to USNRC,

Subject:

St. Lucie Units 1 and 2. Docket No. 50-335 and 50-389. Reply to Notice of Violation Inspection Report 95 EA 95-222 (4 pages)

29. Undated Label, E No.: 95E009. EA No. IA NO (1 page)
30. Undated Label. EF. No.: 94E048. EA. No. (1 page)
31. 96E027 EA: 96-127 (1 page)

Undated Label. END.

32. 04/29/96 Letter to FP&L.

Subject:

NRC Integrdted Inspection Report Nos. 50-335/96-04 and 50-389/96-04 and Notice of Violation (70 pages)

33. Undated 96E003 St. Lucie (1 page) l
34. 03/19/96 Court Reporting Invoice from Brown keporting Inc. (1 page)
35. 03/08/96 Re: St. Lucie Plant NRC. Proceedings before Mr. Stewart D.

Ebneter, from Brown Reporting. Inc. (64 pages)

36. Undated Label. ENO. 96E046 EA: 96-236 (1 page) -
37. 08/19/96 Handwritten Notes (2 pages)
38. 09/19/96 Letter from Stewart D. Ebneter to FP&L.

Subject:

Notice of Violation (NRC Special Inspection Report Nos. 50-335 and 50-389/96-12 (10 pages)

39. Undated Concurrence Page with attachments (23 pages)
40. 11/05/96 Letter from Kerry D. Landis to FP&L.

Subject:

Notice of Violation (NRC Inspection Report No. 50-335/96-12 and  !

50-389/96-12) (3 pages)

41. 09/11/96 Letter from Kerry D. Landis to FP&L.

Subject:

Meeting Summary - Predecisional Enforcement Conference. St. Lucie -

Docket Nos. 50-335 and 50-389 (50 pages)

42. 10/21/96 Letter from T. F. Plunkett to USNRC.

Subject:

St. Lucie l Units 1 and 2. Docket No. 50-335 and 50-389. Reply to a Notice of Violation. NRC Special Inspection Report 96-12 (EA 96-236 and 96-249) (11 pages)

43. 08/19/96 NRC Closed Predecisional Enforcement Conference. St. Lucie ,

Nuclear Plant (22 pages) l

44. Undated Label. ENO.: 96E049 (1 page) l

l Ret F01A-96-485 1

$NO. .DATE' ' DESCRIPTION /(PAGE COUNT) ]

l45; 08/19/96: NRC Special InspectionLReport Nos.-50-335/96-12. j

~50-389/96-12. Pre-decisional Enforcement Conference (47.'  ;

pages)1 i 146, .08/22/96 Handwritten Notes (2 pages)~

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47. Undated Handwritten notes (2 pages) j
48. . Undated Concurrence page with attachment (10 pages) j 49, , 09/19/96 Letter from Stewart.D. Ebneter to FP&L.

Subject:

Notice of j Violation ~(NRC SpecialcInspection Report Nos 50-335 and 50-389/96-12) (33 pages) ,

50. 11/05/96: Letter from Kerry D. Landis to FP&L,

Subject:

Notice of: '

Violation (NRC Inspection Report No. 50-335/96-12 and 50-3P9/96-12) (3 pagos) -

. 51. Undated Notes, prepared by KDL (3 pages) j

52. 08/19/96 Attendance Sheet, USNRC Region-II. Atlanta, Georgia.  !

Topic::St. Lucie Enforcement Conference (1 page) 1

53. 08/19/96- NRC Special. Inspection Report Nos.'50-335/96-12.  !

50-389/96-12. Pre-decisional Enforcement. Conference  :

(67 pages)  ;

54, 08/05/96 Letter from Kerry D.-Landis to FP&L.

Subject:

NRC .;

Integrated Inspection Report 50-335/96-09, 50-389/96-09 and  !

Notice of Violation (51 pages)-

Corrective Actions (68 pages)

.55. l Undated 56, 11/26/96 Letter from Albert F. Gibson to FP&L,

Subject:

NRC Special I Inspection Report 50-335/96-22. 50-389/96-22 (21 pages) l

57. 11/26/96 Letter from Albert F. Gibson to FP&L.

Subject:

NRC Special Inspection Report 50-335/96-22, 50-389/96-22 (20 pages) .i

58. 12/10/96- Enforcement Conference Agenda. St. Lucie (10 pages)
59. 12/10/96 Florida Power & Light, Proceedings before Stewart Ebneter, from Brown Reporting Inc. (108 pages) 4
60. 12/10/96. Emergency' Preparedness NRC Inspection Report Nos.

50-335/%-18 'and 50-389/96-18. Pre-decisional Enforcement Conference (23 pages) 4 J

61. 12/10/ % Handwritten notes (2 pages) i l

Re: F01A-96-485 I

l NO. DATE DESCRIPTION /(PAGE COUNT)

62. 12/10/96 Emergency Preparedness. NRC Inspection Report Nos. j 50-335/96-18 and 50-389/96-18. Pre-decisional Enforcement Conference (23 pages) l
63. Undated Emergency Preparedness Program Inspection, St. Lucie Nuclear Plant (2 pages) 64 01/10/97 Letter from Luis A. Reyes to FP&L.

Subject:

Notice of Violation and Proposed Imposition of Civil Penalties -

$100,000 (NRC Inspection Report Nos. 50-335 and 50-389/96-19, 96-18, and 96-22) (22 pages)

65. 11/26/96 Letter from Albert F. Gibson to FP&L,

Subject:

NRC

, Inspection Report Pos. 50-335/96-18 and 50-389/96-18 t (26 pages)

66. 12/10/96 Florida Power & Light. Proceedings before Stewart Ebneter.

Chairman, from Brown Reporting, Inc. (29 pages)

67. 10/31/95 St. Lucie Enf Action. EDO Questions (3 pages)
68. 10/27/95 Briefing on Use of Discretion to Propose Civil Penalty for Inoperable PORVs at St. Lucie (6 Pages)  ;
69. 10/03/95 Handwritten notes, St. Lucie PORV (3 pages)
70. 09/25/95 Handwritten notes St. Lucie PEC (3 pages)
71. 09/25/95 Handwritten notes (1 page)
72. 08/22/95 Letter from D. A. Sager to USNRC,

Subject:

St. Lucie '

Unit 1. Docket No. 50-335. Reportable Event: 95-005 Date of Event: August 9. 1995. Pressurizer Power Operated Relief Valves (PORV) Inoperable due to Personnel Error (8 pages) 73, 11/13/95 Letter from Stewart D. Ebneter to FP&L.

Subject:

Notice of Violation and Proposed Imposition of Civil Penalty -

$50,000 (NRC Inspection Report No. 50-335/95-16 and 50-389/95-16) (49 pages)

74. 12/06/95 Letter from J. H. Goldberg aJameslieberman,

Subject:

St. Lucie Unit 1. Docket No. 50-335, Inspection Report 95-16, Reply to Notice of Violation EA 95-180 (9 pages)

75. 01/02/96 Letter from Josepn R. Gray to FP&L (1 page)
76. Undated Facsimile Transmittal to Casey Clark.

Subject:

St. Lucie Enforcement Action (1 page)

h Re; F01A-96-485 110 . DATE DESCRIPTION /(PAGE COUNT)

77. 11/01/95 Fax transmission of FP&L. St. Lucie Unit 1. Administrative Procedure No. 1-0010125A. Revision 39 (6 pages)
78. 08/22/95 Letter from D. A. Sager to USNRC.

Subject:

St. Lucie Unit 1. Docket No. 50-335, Reportable Event: 95-005. Date i of Event: August 9. 1995. Pressurizer Power Operated Relief Valves (PORV) Inoperable due to Personnel Error (8 pages)

79. 12/10/96 Security. NRC Inspection Report Nos. 50-336/96-10 and 50-389/96-19. Pre-decisional Enforcement C)nference (13 pages)
80. 01/10/97 Letter from Luis A. Reyes to FP&L.

Subject:

Notice of

.- Violation and Proposed Imposition of Civil Penalties -

$100.000 (NRC Inspection Report Nos. 50-335 and 50-389/96-19. 96-18. and 96-22) (22 pages)

81. 01/10/97 Press Release.

Subject:

FPL Receives Notification of NRC Civil Penalties (2 pages)

82. 01/11/97
  • Newspaper articles (6 pages)
83. 01/10/97 Press Release.

Subject:

NRC Staff Proposes $100.000 in Fines Against Florida Power & Light at St. Lucie Nuclear Power Plant (1 page)

84. 01/07/97 Office of Enforcement Notification of Significant Enforcement Action.

Subject:

Proposed Imposition of Civil Penalties - $100.000 (1 page)

85. 11/15/96 Letter from Albert F. Gibson to FP&L.

Subject:

NRC Inspection Report Nos. 50-335/96-19 and 50-389/96-19 (13 pages)

86. 10/25/95 Letter from Stewart D. Ebneter to FP&L.

Subject:

Complain.t of Alleged Discrimination (7 pages)

87. 10/06/96 Letter from Stewart D. Ebneter to FP&L.

Subject:

Complaint of Alleged Discrimination (4 pages)

88. 10/06/95 Letter from Stewart D. Ebneter to FP&L.

Subject:

Complaint of Alleged Discrimination (5 pages)

89. 01/04/96 Memo from Bruno Uryc to Ellis W. Merschoff.

Subject:

Phipps  !

v. Florida Power and Light Company. Department of Labor l (DOL) Case No. 94-ERA-53 (6 pages)
90. 03/22/96 DOL Log Sheet (1 page) )

i

o Re: F01A-96-485 N0. DATE DESCRIPTION /(PAGE COUNT)

91. 10/17/95 Handwritten notes, phone call (3 pages)
92. 03/13/96 DOL Log Sheet (1 page)
93. 08/29/95
  • Newspaper articles (5 pages)
94. 09/22/95 Letter from Bruno Uryc to U.S. Department of Labor,

Subject:

Request for Access to DOL Case File (3 pages)  :

95. 01/04/96 Memo from Bruno Uryc to Ellis W. Merschoff,

Subject:

Phipps

v. Florida Power and Light Company, Department of Labor (DOL) Case No. 94-ERA-53 (6 pages)
96. 10/06/95 Letter from Stewart D. Ebneter to FP&L,

Subject:

Complaint of Alleged Discrimination (4 pages)

97. 09/22/95 Letter from Bruno Uryc to U. S. Department of Labor.

Subject:

Request for Access to DOL Case File (3 pages)

98. Undated Florida Power & Light Company St. Lucie Unit 1. Operating Procedure No. 1-0250020. Revision 35.

Title:

Boron Concentration Control - Norman Operation (14 pages)

99. 12/01/95 Florida Power & Light Company Nuclear Energy Deprtment.

St. Lucie Plant - Preparation. Revision. Review / Approval of  ;

Procedures (4 pages) 100. Undated Florida Power & Light Company St. Lucie Unit 1. Operating Procedure No. 0010120. Revision 79.

Title:

Conduct of Operations (17 pages) 101. Undated Florida Power & Light Company, Docket No. 50-335. St. Lucie Plant Unit No. 1. Facility Operating License (4 pages) 102. 08/28/80 Note from Darrell G. Eisenhut to R. Tedesco. T. Novak, and G. Lainas (3 pages) 103. Undated St. Lucie Unit 1 FSAR (2 pages) 104. 03/12/96 Letter from Albert F. Gibson to FP&L.

Subject:

NRC -

Inspection Report Nos. 50-335/96-03 and 50-389/96-03 (29 pages) 105. 03/25/96 Office of Enforcement, Notification of Significant Enforcement Action.

Subject:

Proposed Imposition of Civil Penalty - $50,000 (2 pages)

Re: F01A-96-485 N0. DATE DESCRIPTION /(PAGE COUNT) 106. 03/28/96' Letter from Stewart D. Ebneter to FP&L.

Subject:

Notice of Violation and Proposed Imposition of Civil Penalty -

$50.000 (NRC Inspection Report No. 50-335/96-03 and 50-

, 389/96-03 (16 pages) 107. 03/08/96 NRC Closed Predecisional Enforcement Conference. St. Lucie Nuclear Plant (20 pages) 108. Undated Letter from Albert F. Gibson to FP&L.

Subject:

NRC Inspection Report Nos. 50-335/96-03 and 50-389/96-03 (30 pages) 109. Undated Notice of Violation (6 pages) 110. Undated Notice of Violation (6 pages) 111. 08/05/96 Letter from Kerry D. Landis to FP&L. Subject NRC Integrated Inspection Report 50-335/96-09. 50-389/96-09 and Notice of Violation (52 pages) 112. 09/12/96 Office of Enforcement Notification of Significant Enforcement Action.

Subject:

Notice of Violation and i Exercise of Enforcement Discretion (2 pages) 113. 09/19/96 Letter from Stewart D. Ebneter to FP&L.

Subject:

Notice of Violation (NRC Special Inspection Report Nos. 50-335 and l 50-389/96-12 (10 pages) 114. 08/19/96 NRC Closed Predecisional Enforcement Conference. St. Lucie Nuclear Pldnt (24 pages) 1 115. 08/19/96 NRC Closed Predecisional Enforcement Conference. St. Lucie Nuclear Plant (25 pCes) 116. Undated Schedule for EA 96-236 and 96-249 Severity Level III Violation - St. Lucie Inadequate 50.59 (2 pages)  !

117. Undated Letter from Stewart D. Ebneter to FP&L.

Subject:

Notice of Violation (NRC Inspection Report Nos. 50-335/95-20 and 50-389/95-20) (5 pages) 118. Undated Letter from Stewart D. Ebneter to FP&L.

Subject:

Notice of Violation (NRC Inspection Report Nos. 50-335/95-20 and 1 50-389/95-20) (6 pages) 119. Undated Notice of Violation (5 pages) j 120, 11/14/95 NRC Closed Predecisional Enforcement Conference. St. Lucie ,

Nuclear Plant (17 pages)  !

1

i Re: F01A-96-485 l

N0. DATE DESCRIPTION /(PAGE COUNT) 121, 10/26/95 Letter for Ellis W. Merschoff to FP&L.

Subject:

NRC Inspection Report Nos. 50-335/95-20 and 50-389/95-20 (15 pages) 122. Undated Names and Titles of Russian Visitors (2 pages) 123. Undated Letter from Ellis W. Merschoff to FP&L.

Subject:

NRC Inspection Report No. 50-335/95-16 and 50-389/95-16 (18 pages) 124. Undated Licensee (2 pages) 125. 09/25/95 NRC Closed Predecisional Enforcement Conference. St. Lucie Nuclear Plant (18 pages) 126. Undated Chronology of Review of St. Lucie PORV Case (2 pages)

, 127. Undated Briefing on Use of Discretion to Propose Civil Penalty for -

Inoperable PORVE at St. Lucie (6 pages) 128. Undated Briefing on use of Discretion to Propose Civil Penalty for Inoperable PORVs at St. Lucie (6 pages) 129. 11/07/95 Office of Enforcement. Notice of Significant Enforcement Action.

Subject:

Proposed Use of Enforcement Discretion and Imposition of Civil Penalty - $50.000 (2 pages) 130. 11/13/95 Letter from Stewart D. Ebneter to FP&L.

Subject:

Notice of Violation and Proposed Imposition of Civil Penalty -

$50,000 (NRC Inspection Report No. 50-335/95-16 and 50-389/95-16 (12 pages) 131. Undated Pages from Notice of Violation (3 pages) 132. Undated Enforcement and Investigation Coordination Staff.

. Region II. Reference Package. EA 95-180 (4 pages) 133. Undated Chronology Unauthorized Individual Entering the PA after Termination (3 pages) 134. 11/12/96 Draft Notice of Violation. St. Lucie Plant Inspection Report Nos. 50-335. 50-389/96-18 (3 pages) 135. Undated Letter from Ellis W. Merchoff to FP&L. Subje:-t: NRC Inspection Report Nos. 50-250/93-23, 50-251/93-23.

50-335/93-21 and 50-389/93-21 (6 pages) 136. 12/29/94 Facsimile Transmittal to Beall/Satorius from Uryc (10 pages)

r 4- ,- + .-

Re: F01A-96-485 t

N0. DATE DESCRIPTION /(PAGE COUNT) 137. 08/22/95 Letter from D. A. Sager to USNRC.

Subject:

St. Lucie Unit 1. Docket No. 50-335. Reportable Event: 95-005. Date  :

of Event: August 9.1995. Pressurizer Power Operated Relief Valves (PORV) Inoperable Due to Personnel Error (8 pages) 138. Undated Memo from Ellis Merschoff to Bruno Uryc.

Subject:

Similar ,

(Repeat) SL-IV or SL-V Violation: No Escalated Enforcement Proposed (29 pages) >

139. Undated Notice of Violation (6 pages) 140. 6/12/96 Facsimile Transmittal from Bruno Uryc to Joe Gray (2 pages) 141. Undated Letter from Stewart Ebneter to FP&L.

Subject:

Complaint of Alleged Discrimination (4 pages) 142. Undated Letter from Stewart Ebneter to FP&L.

Subject:

Complaint of Alleged Discrimination (4 pages) 143. Undated Letter from Bruno Uryc to U.S. Department of Labor.

Subject:

Request for Accession to DOL Case File (3 pages) l 1

I i

DECEV.Of"E & PLIMPTON ees isTH STREET. N W. 2l AVENUE GEORM V REED COURT. 6 WTE 875 THIRD AVENUE NEW YORK, NY 10022 M*ao2 m' m' TEKOOMER Goa a83-SHS -

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N[selo 79:e TEUECOP4ER 962 20109828 h*3$# m TEEOOPER 06 U L32 7995 November 14, 1996 FO!A/PAim Russell Powell Case No: 94-485 Chief of the FOIA/LPDR 77-/f 94.

Nuclear Regulatory Commission () ele Rafd g e g,_

Mail Stop T6DB gg Washington, D.C. 20555-0001

Dear Mr. Powell:

This is a request under the Freedom of Information Act, 5 U.S.C. S 552. I request that a copy of all records and other documents that fit the following description be

sent to me
1) All records or other documents from January 1, 1993 to the present that are not currently in tha public documents room and that relate to Florida Power and Light's St. Lucie Nuclear Power Plant (Unit 1 and/or Unit 2).
2) The number of i$1spection hours (by quarter) devoted by the NRC to all licensed nuclear plants in' region 2 since January 1, 1993.

In order to help determine my status for the ,

purpose of assessing any fees, you .should be advised that I represent a company, and I am seeking information for use related to the company's business.

L Please advise me of any fees associated with processing thi's request.

Sincerely, Neil S. Binder 20280632.01 YlS&'_

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.. 4 Plere Power & ught compeer. P A ses tal, Fed Plwee, rL 3W544tal I

585 %

L 9641 March 6,1996 l

U. 8.Huoleer Roeulatory Commission Attrt Document Control Desk Washington, DC10655 Re: St. Lucie Units 1 and 2 Docket Nos. 60435 and VA89 Escoes Dilution of the Reactor Coolant System Due to Personnel Error Nuclear Problem f%oort 96408. ReYlSlon i As the result of an event involving the exooss dilution of the Reactor Coolant System at j 8t. Lucie Unit 1 on January 22,1996, Florida Power & Light Company (FPL) ini!!ated a l

cross 4unctional investigation to determine root cause and corrective setions. On February 21, 1996, an interim Nuclest Problem Report (NP) 96008 was issued discussing i preliminary conclusions.

The purpose of this letter is to forward to the NRC Revision i to NP 96 008 which, in I addition to presenting the resuits of the original cross-functional investigation concoming root cause and correctiva actions, includes the event analysis and conclusions of an independent, non-FPL expert on nuclear plant operations and event analysis, if you have questions on the attached report, please contact us, V truly yours, d #,f b, Vice President St. Lucia Plant Attachment

! WHBIEJW oc: Stewart D. Ebneter, ReDional Administrator, Region 11, USNRC, Atlanta, GA 8erdor Resident inspector, USNRC, St.1.ucle Plant l

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ST.LUCIE PLANT

! NP.700 PROBLEM REPORT 96-008 L EVENT TITLE ,

1 Besses D5ution of the Ranctor Coolant Symma Due to Personnel strar.

!. St.Lucie Unit 1 EventDese: 22 January,1996 i

l g, IMITIALyt ANTCONDITION5 i

j Unit I was at 100 percent power, steady state operations.

j BL EVENTEEOUENCE i~

! At appreadmassly 0220 on January 22,1996 normal reactor fbal depletion resulted in an inmenad renseor coolant cold leg temperature (T,) or54s.7F. The Board Reestor Control i

Operator (BRCO) commenced a dilution to the Reactor Coolant System (RCS)in order to i restors T. to a temperature of $48.9F. He began a manual dilution with Priney Mabeup Waser (PMW) at appituimately 38 spna directed to the auction of the IB Charging Pump at

! .y% 022s Accordlag to the BRCO, shutly aAer the dilution was h

! mumaciator z.9, 't.ub. Wata supply strainer 4/p re", was received. The anCo at the 4 asserals ist the visinity ofRTOB 105 (this is the lacedon of the controls ihr the horetion and

! mudos syman) to soimowledge this slerm on RTGB 102. Ator responding to the slana, the l BRCO requested that the Desk RCO (DRCO) relieve hhn at the controls so be might go to j the kie 6en, NDECO moved into the vicinhy of1T05-103 The dilution in progress was l not -=la=*ad by the BRCO during the short term tumover process. The BRCO then

let the 'at the controls area' and went to the kitchen to prepare his meal.

l Apperwi==+=iy Ave sninutes later, the BRCO returned to the control room and heard the FMW integrator "dicking". '!he BRCO realised the addition of primary mabeup weser to the

RCS was sell in pmgress and immediately took corrective actions to secure the Sution and j aa===naad borating the RCS. The BRCO commenced boration to the auction of the 18
Charging Punp fbr a total initial addition of approximately 26 gallons of borie acid and intinned the DRCO and the Nuclear Plant Supervisor (NPS) ofhis acticas. At appronhnstely
the same ihne the BRCO was taking corrective action, annunciator M-16 "RCP CONT j RIDOFF FAB 85 HIGH" alarined, due no a higher than nonnal Volume Control Tank (VCT)
presses 6om the increase in VCT level and Pressarizar level as a result of the expansion of i RCS inwensory &om Tave increasing. The Assistant Nuclear Plant Supervisor (ANPS) was l ====amad by the NPS to the control room Rom the khchan to amist in actions to return the
plant to within nonnat operating parameters. T, was obearved to be greater than 549F.  !
i

, With the borstion started, the NPS and STA reviewed the Technical Spenineadoes and ]

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entered a two hour action atstement to restore RCS T, to less than or equal to $4pF la

{ essordanos wkh Technical Speal$ondon Lksidas Condition of Operados (LCO) 3.2.5, DNB j Parameters. At 0314, ladiosted T, was rearned to less chas 549F, and the LCO Asdos Statement wee ashed. At other permanors mached normal levels concurready. As was later  ;

celeulated, and condemed by recorded plant ladiendona, the highest reestor power and RCS ' I i oold les temperature during the event was 101.13 peroest and $50.aF (single point J i maximmun).

BeAme the new let the site that morning, several reviews of the event began. De erow shit shpemision verbeHy sounseled the BRCO for leaving bla station while a dilution was in psogress. The ANPS also wrote a nod 8eados of the event in the ima otDesa Sheet (DS) l l

i 7 (Operadoes Department Problem Report, Conduct o(Operations procedes) and mausd

a paper copy to the Operadoes Supervisor. no ANPS provided a verbal motiSostion ofthe

! event to the Operations technical supwvisor during his nonnal morning tour of the consol j rooms. He gTA papered a drat In House Event (IHE) summary 9640s to convoy ths hets

ofthe event to the she menessmars and to initists a STAR lbr root cause determinatics. The

, STA also requested that the Human Peribnnance Evaluation System (HPES) CoonEnster be i saBed out to invesdgets the event. He HPBS Coontinator arrived onsite at 0515, reviewed l the dreA IHE and conducted intaviews wkh the personnel involved. At the 0740 maming

maansement phone eau, tie operadom supervisor and the Plant General Manegar were l provided with a oopy of the EE. On that same day, the operadons technical apervlaar bases an event review which included discussions with the reustcrew, Eco chronologimi l review, the DS 7, training and per$mnenos appraisals seisted to the BRCO. At the and of the day, the 4 #-v5 technioni supervisor recommended to the Operadoes Supervisor that the anco be amovat a m watch si.ndes duda. He also motised tlw NRC Rasident of the l lavestigation status.

l On the ibliowing day (January 23), the Operations technleal supervisor conducted a fbet

Saling
nesting with the crew and bergaining urit w,,.E =46. Followingthatmeeting,the
Operadons 6; r ' = canarred in the suspension of tlw BRCO Rom watch standing duties.

j no Opemtions technical supervisor provided the NRC resident with an update to the ovest. I

! On January 26, the um was updated by the HPES Coordinator to include at of the thats l leamed about the event dudng the weelt. At the direction of the Plant General Manager, on 1 i January 21,199d, a cross ihnetional team was fbrmed to review the event and subsequent i

! plant staffregonse.

! i En M i The team identifad two primary pmblems fbr this event. They are discussed in detail

below.

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A naadvky evoludon was inkleted wkbout adequate controls, f

I Routine boros dDutions to snaintala 100 percent power are not treated; l'

heportance as other reactivity maassemens ev j l

maintain 100 peromat power. (

i t 4. 9

  • )'%4 l 14 5 The BRCO, i
1) Copiitive error on the part of the BRCO who initisted the dilution WE
as part of his normal g
- "* ties, tr+r'u the need to du itwas asomsarytoiriest w

^

RCS. The PMW h$setion rate was to be about 38 gallons per minute; th dhmian evoludon was to haw inmed less than one minut the ERCO tiled to Adlow k to km proper completion la that he .g- M to a (B 9) and subsequently let the inunedisse area.
s. De opennor's integrated performance was not adequately evaluate .

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The BRCO's training and pernamnel records were reviewed Ibr insight lato perfoemanos. De subject roosived as 'Unsatisihatory" reting in his Ml l evelanden (controlboard operations) and was placed on the operator E ;

AAer re==#=*iaa and . #4=, the subject received an individun! radas of!

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  • sat /warninal- saany signisosat." Upon anther ---iw the subject roosived individual rating of "Sadhy (6/2/95). The BRCO was idend6ed in a Training l l

deparament memo (9/8/95) as a Historical Poor Performer due to fld  !

l June 1995 aad sisadator perfbrmance exam in May 1995. In particular, the m that he is "la too much of a hurry, and doesnt communients well." Other note l observadons taken kom sinudator evaluation surnmary fbrms and perbrmanos r i

a i - "need to work on w.ar. cations" and 'should mark timaflevel den fnonitoring containment sump" simulator evaluation of 4/29/94;

- %iled to realise that pressuriser safkty valve was open" - simulator evalunden of11/6/95;

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  • easily diverted and needs to improve in this area' - performance review 11/1(Wp4.

This review of training and performance suggests that the qualification of the 3

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JfeHis3 'Is0 TUE 22:34 ID: ,, ,TEL to: 505 han

j i L.es4 Mueh8,1996 j Aa a- = Esvision I a

j ladividual abound have been more closely scrutinised by C;_-e- and Tralaing wanagsmsme. j 3

j b. There was no supervisory involvement at the start of the dilution.  !

  • l

- Neither the diludon procedure, OP 14250020

  • Boron Coassetration Control - l Normal C,_ J=", nor the "Condum of Operations' procedure requim the BRCO to j
ladbrun the ANP5 or other wasolutanders of the initletion of any boredom or dilution evolutions. Berating or diluting the RCS changes the remotivity of tbs roaster core and l should be considered a signiSonat evolution. Olven that there was no precedurai

!' regidrements er any type ofactincation at St. Lucie, the BRCO was act de5cient in this aren. Had this been a plant policy, the ANPS (or other watcheadars) would have been aware of the evolution and may have recognised and corrected the error of the BRCO.

l 2) Conduct of 0perations espectadons are not ibily undermood or consistently applied.

The BRCO let the RTGB ares and went 'over the line" to the kitaban. During this

< traaddon, he turned over the RTOB watch to theDRCO who was raurning Dom the idechen. i Appendix D of the " Conduct ofOperations' procedure provides lastruodoes br providlag a sunurver dbr 'short tena relief' which is de8and as less than two hours. Asconing to the

, c::M, adaimum turnover requiramame consist of providing: a generalwatch station  ;

status; ee'.nonnel conditions; and tests in progress. Operadoes --- ;:-M supsenaden j' is that short tonn tumoveris applied whenever a watchstander goes "over the line' and is out

! ofans ofalght ofthe board. However, based on interview of seven operators aRer the event,  ;

j this espectation is not clearly understood by operators. A proper tenover may have i prompted the saco te reenil as ddution sad take appropriate aedon. Misunderstanding or l such a ihadarmental policy indicates a weakness in monitoring of the i ,'n "="-: of i policies and a=pama*iana by F-g "

) Managements apostation of' verbatim" compEance to procedure does not ibHy recognize

=

l the qualhy of current procedures nor accountability for instances of non -:=5"-

l Procedure OP.14250020 did not contain auf8cient detail to permit "W 0# complianos, yet none of the operators idendSed the need fbr a procedure change. In fact moa of the, l opermors interviewed aAer the event felt that this evolution abould not require a procedure.

Theyinitit was "skR! of the craA." ,

i 3) Recent plant events involving operstor personnel errors have been previously identined and morisadvs actions have not been completely afthetive.

A QfA assessment, Teobnical Review Report #1TR 95-023, performed at the request of the site Vice Prteident, reviewed absteen events that occurred sineq August 1995, identiSed I that many of the events' corrootive actions did not go thr enough to address al potential causal fbstors. R concluded that many similar events had a medium to high probabuity Ibc recurrenos.

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TEL to *M Jm-tss 'w luE. 23:34 in:

1 IA641 Mmeh6,1996

Aussbauet Redsiss t i

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4) De pines % Operedng Esperience Feesheek propata did not respond to simDar reactMty

! managenom evens a wher nuelar pieses.

i Bessaso ofa number ofindustry events invoMag remotMey management, DEPO leaued a j SigniSommt Operating Experience Report (SOBR) 94-2, which alerted the industry to the

! Importanos ofremmMay management dwing nonnel openslan. Dis report included a diinden event very simuar to the 8t. Lucie event which occuned W Turkey Pains in October 1993. ,

In resposihig to the report, the plant did not identdy routine dilutions u an evolution that 3

j f*1ulred specialstantion.

4 j 8)IJoensedOperatorhtd8a=*= Training houses principauy on abnormal or emergency situssions.

i Lasson piens and simulator experienes deal almost esclusively with abnormal or amorpacy

altuations. As a result, routino evolutions, which are oAen the procursor of abnonnel or
unerpeney events, tend to have less signl8canos.

l 6)The plant's Self Aassesment Programs have not been fbuy edisctive in pteventing

resurrenos ofpabiens. .

1 As discussed earlier, the Quality Assurance organiandon has ideadfled opasser i l l

partnnance shortaomings where conective actions have not been Adly ofRietive.

w!d ' ==- . M .m du.h the avsen =+M -ant abr+ha+ ++=

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1) Plant procedures do not specify the preArred method of making boration or dilution
changes.

Operating Procedure OP 1 0250020 " Boron Consentration Control-Nonnal Operation' allows several Bowpaths fbr dilution. The procedure does not state which flowpath is i presured ihr maidag boron concentradon cunges. A note in section 8.1.7 states that l ' Makeup tom the Baron conoonestion control system can be directed to either the VCT (br l

long tens alRects, in any mode of operados) or the Charging Pump suction (k short term adhots), in the MANUAL or BORATE modes of operation.' Seedon 8.5 " Manual Mode of Opension" alkms blanding directly to the VCT or um of a diroot path to the charging pump ansion. Duution via the Volume Control Tank provides a slower remotMty response and in i this insident may have alkrwed fbr rooovery pdor to power awalmian. Diludon via the VCT

also lengthens the duration of the evohntion. Operations ums* evaluate the various Bowpath opdons ihr maldag baron concentration changes, idendfy the preferred methods and revise

! proosdans sooonnnsly.

2) De pmodos ihr operating at the Technical spar *=*= limit for 7, provided no operatig j surgia.

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.Needu *1s0 TUE 22 35 ID TEL NO 8009 POS i 4

i Mush 6,1986 L.8641 Ammemes assisinaa j

l For FEL Unk 1, the lindt ibt DNB conalderations fbr cold leg temperature is less than or eq%I to 549F. The St. Lade plant prestlos to operate cold leg temperates at the Technica!

aM Emit of 549F did not provide margin for error. Changing RCS beson

. onnemerullen is a narinal plant operation, compensating ihr long term remotivity edbets, such l as sat depission, annon insidup and demy, plam stenups, shadowns, or changes la reamer power. As the cycle progresses, the RCOs are required to make more toquent reestivity i' manipulations, seesiting in a higher chance of occurrence of an error due to lessened sense

! cfsunrenessorimportanes.

3) Iask of annuncletion and indiention during this event.

A semand room alann . 4 ^; to a dilution evolution in progress annunciates only when f the diuties becomes amassive. '1he only alarm to annunciate in the control room as a resuk j

of this over<lilution event was M-16, RCP CONT BLDOFF PRESS HIGH, which wee

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i caused by rising Volume Control Tank (VCT) Pressure as reactor coolant inventory inernmend. An alarm for RCs hish cold leg tanpwature is available, but to avoid admass j nierse (operator distraction), the alarra setpoint is approximately 3F greater than the j applicabia Uraiting Condition Ibr Operation of 549F. Similarly, a Delta T Power alarm (Point ID 142) on the plant DDPS computer is no longer mairdained in a Amational status.

4) The UFSAR has not been maintained current with regard to operating pracrinas l

PSL.1 UFSAR 5ection 9A.2.3 prknarily discussen boration and dBution utillaing the

automatic mde oroperanon. utos disoumion is provided regareins sin mammi nede or i operation. No specific discussion regarding dilution directly to the charging pump sustion
is provided in this sootion of the UFSAR. St. Lucis operators have historicany mada l

reestivity charness via the manual mode of operation. Discrepancies between the PSL UFSAR

and adsting operating practices are a recognimod problem at St. Lucis. A roosnt QA sudit Finding and anNRC deviation have provided examples of this issue. The UFSAR has been meistained surrent with regard to physical plant change via the plant charigeWIAaaelan
(PC/M) process The UFSAR has not always been maintained current with regard to.

j desmiptions of operating practices, procedures and adannistrative details. The UFSAR has

not been routinely referred to during the periodic review of plant procedures or during the procedure revialon process to ensure continuing agreement with plant operating precdosa.

FRDBIRM1; i

The plant staffs recognition of this event's signticance was slow.

I Raet Causer l The root cause of this probiern is lack of a well defined threshold for recognizing safbty I signlSonnos. The opemaing crew quicidy diagnosed the problem, took quick and appropriate l

corrective action prior to challensing any safbty systems and reported the event in that i

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  • Mash 6,1986 1441 Raviden1

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eosdWit. W should have recognised that In House Event Reports and IG'E8 l laterventices identify issues of asoity signl5 canoe which should be bliowed up snoes j

j agresively.

l Osatdbatins Faeterm The In house Event susnmary had InadRelanr detall to gain management attention and

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managsmas did not respond aggressivuly so an wyd-mad reactivity changs event, agar 1

ofdemisonnes, spedssey, the DIE did am contain tbs inimandon that tio BBCO had is i

j a reestivity change unattended. AdditioseDy, bened on the observed indicadons o(Digital i Desa Proessairg System (DDPS) digital display provided by the operating crow and NPS to the STA, the DIE reported that the peak reactor power m 100.2 perses. Subsequent detailed analysis tsveeled that reestor power peaked at 101.13 peresnt. Subsequent to the j

event, Plant and C;_d-= management did not pursue details surrounding the duution la d a time tems consistems with the event's signiSonnes.

At _,,+_' - MiOMS, the Operadons Supervisor made his reudos phone eau tem odRdte

to the sontrot rooms Air a unit status. De NPS reisted details about the event per this phone i

ensversation. De discussion included corrective actions, the Techrica! 5 paean,means trO essered and edted, the RCO Chronological log entry, fadividuals involved, initiation of as DIE and D3 7. (Appendix E of the Conduct of Operations procedure requires the ShlA l s:;P= to make prompt verbal notisondon ibt unasplained or unpisaned renadvety changes.) Aalndested above, the ANP5 was prompt with compladon of the DS 7 bsGus went off ablA. Esview of the D8 7 revealed that the speciSc detail related to the BRCO i

leaving a reactivity change unsttended was.not included la the report.

_Addwaanim- _ " t:ad drah; the event review wt&h warrant fbrrher irrv==*iaarlaa i jeduds;

1) The plant staffs inhialinvestigation of this event was less than adequate.

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I Thers were severallattial lavestigations into this event, all of which were independent of l

each otherto alares degren. Prior to the end of the shiR Monday, severalindependent event l

reviews took plass. De Operadons answ shiR supervision evaluated the event as warrantin

l doownertados to the Operations Supervisor via a DS 7. The STA also wrote an DIE to site l' management k the event. The HPES coordinator interviewed the personnelinvolved. On l' Tuesday, Operades supervision conducted a ihet finding meeting with the crew. On Wednesday, Operations snanagement conducted a review of the event. Nine days aAer the l et ant, a cross 8medonal team was ibrmed to review the event and aabsequent plant response.

Casertaming caussa to the slow and 'mdependent efforts included lack of site procedures k keegrated event respaans investigation, root cause analysia, and self assessment.

AdditionaDy, the level of detall in existing procedurus and guidelines is inadequase in that:

- DS 7 does not contain requirunents ibr a significant level of detall 1

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4 J4HK3 'ge 71K 22:37 in: E@ #009 Pio r .

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wa. nae,ises .a i l

j - The HPES guideline does not contain repordng time or audience requirements, and, )

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- thee is no ptooedural guidance on classi8 cations of event s 4 and appropriste levels l j

afresources required br event'. - 1" 4

l 2) De asif assessment by the openning crew was less than adequate. i 1  !

) Tha CW-:= orew shift supervisor verbeNy counseled the RCO br leaving his station wkh a dilution in progress, but did not induds this level of detail in the DS 7. A thoroudi esif:

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- ofthe event should how been conducted by du crew prior to their laeving es she en the day ofthe event. Conotuting osuses to this condidon were the absenes of a desmitivli sise entf =e policy and procedure and no continuire training provided to operasions l

i personnel on self assessenests and perecenet enor analysia.

! 3) The transeur aflessons learned Aom a similar event at Turkey Point to St. Lucie was less than adequate.

i j As previously dia===ad, a similar event to this one has previously occurred at herkey Point, with simRar countermeasures appled.

L ANALYSTE OF FHYEICAL PLANT nu'inDONSE DURING EVENT l

The key safety parameter associated wkh this event is departure &om nucients boiling j j P (DNB). There were two plant operadng parameters that were notably affseted by this eve rosator coolant sold les temperature (T.) and reactor power. Per Technient speelesseion l 3.2.5, T, is limited to 5 549F and is nonneDy controlled et about 548.9F. As a result of th Amina. T, increased to a peak value of 549.7F (per ERDADS). Graphical data showed T.

l i above 549F lbr approximately 50 minutes. Reactor power is nonnaby maintained at 5100  !

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peroes. From a review ofERDADS (Q power) and onlorimetric power data, it een be inferred that calsd.Lianc power did not enosed 101.13 percent. Interpolation of the dass l l '.T.stely fbur minutes and above showsthat reactor power was above 101 percent fbr app 100 percent br eg=l~# 50 i minutes.

UFSAR section 15.2.4 pnwides an analysis of the design basis boron ddution events.

l

. These events assume the h(estion of unborated domineralized water into the RCS of 132 3psa (3 charging pumps x 44 gym / pump). The analysis notes that boroa diludon events are relatively slow events and that there are numerous indications and alanns eveRaide to opentors (e.g., boronometer, VCr level, makeup Sow, VCT laolation). However, should diksion proceed without operererintervention, the event would be terminated by the TMLP i

or venable high power trip. DNB rado (DNBR) Emits would not be exceeded in auch a cas l l

  • ne subject dDution occurred at a rate of 38 spa. Thus, the event is clearly esveloped by th l

edsting UFSAR analysis fbr a baron dilution at power event. Additionally, a core flus map l

generated Gom DDPS data polled at 0300 (ater the event) and compared to the data tom l-0200 (bette the event) Indicated a normal Sux distribution.

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JAN4iD ' lie TUE 22:37 ids TEL to: Mil 09 Paa 7

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l 1A641 Me d s,less Aamulisenst RadsionI h ===* islam, the baron dRution event ofJanuary 22,1996 was within the design basis and aselysis ofthe plant and did not present a chauenge to plant saasty systems or pose a risk to the beshb and astsy ofthe public. The event was terndnated by operators prior to the ossa ,

of the stanns and automatic presodve maions provided Ibr such an event. The lleens condition of manhnen steady-state thennst power was not violated.

E conRECTIVEACTIONS Essonnel

1. De BRCO was removed Dom iloensed operator duties. Cosnplete

- 2. Hanna Resources and Training are developing an assessment and remediation plan ihr possible return of the BRCO to licensed operator duties. Compissa

3. Lassons learned Rom this event were reinforood via supervisory expostations h to Shift Technical Advisors in the areas of. Sensitivity to plant events, k>

House Event summary securacy and cosapleteness of supponing data, and to CFR 50.59 twieurs. Complete ,

4. The Operations Supervisor has disciassed with each NPS the purpose and thresholds of Appen6s B, Conduct of Operations, and the necessary nosi$ostions. Complets l

. Premearmamamunaannennales

5. The Conduct o(Operadons Procedure was revised to include the ibliowing

. Board walk down is now included as part of the "Short Term Turnover" process, I - Direct supervision of reactivity changes is required by a Senior Reactor Operator, 1

j - Rasetor Control Operator is to remain at the controls during all reactivity changes e in progress,

- Reactivity changes shall not be tumed over while in progress.

Complete

' 6. Operations wiu revise the 'CW of Operations" to clarify ' abort tenn turnover".

Examples ofwhen "short term turnover' is required wiu be included in the revision. This rwision should be communiosted to Operation's personnel by Night Order and dissuased

! with operating erswa Training should reinforos these expectatlons during training 2 seestons and M'ay should monitor ks efectiveness. Complete

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- aww lue 22s un . m. re: r.e m 1.

MkM e Ansshant Revieles t

7. Engineutng has perfonned a $0.59 ovaluados to reanst Cp--4=/s practice ofusing the "assual" mode of dilution and boration. (This 50.59 win be included in the nest annual update to theUFSAR.) Complete .
8. Engineering has reconvened the UF8AR review team to complete the review of the IE'5AR versus pleas procedures. Sampling completed 2/29/96. Full soops and schedule I dueby 341/96. DanDenver
9. Opumions wil revise the Tonduct of Operadens' procedure f ,

s a suSalentlevel ofdeteE inDS 7 reports so rannagement wu! have adequase indm _ m dbr assessment of tho problens. JetWest-Due 341/96

10. System and t'a=paaaar Engineering is t':;'sg an Event Response procedure. 'llie procedure will hudude or reference: Root Cause Analysis techniques, event severity elassinostions and resouraea required for analysis. This procedure will also include supectations 1br the team to include cross imetional raembership front SCE, Operadons, Engineering, Malataname and QA. Turkey Point's Evem Response Procedurs is under review tbr incorporation at St. Lucie Chuck Wood -Due 3/15/96
11. The procedurs upgrade process wR! lnclude UFSAR review to identify inconsist-dan ibt
oorrection. Complets I 12. For the balance of plant procedure not captured in the upgrade process, Informados i Services wlR esaurs that the UFSAR is examined during the three year procedure review process and that inconsistencies are noted and corrected Jim Holt - Due 3/15/96 Equipment Pardbemanaa
13. The Plant Genomi Manager has reemphasised the reduction of nuisance alarms to at line organisstloss to support the " blackboard' concept for operations. Compiste I
14. Engineeringis #  ; the current control room annunciation for poNWn =

j to help lbous awareness of reactivity changes Dan Denver - Due 3/31/96

15. OST will survey the industry on the use of automatic and manual boration and iRlution
controls to benchmark St. Lucie and detonnine best means of reactivity changes by 1

! ehemicalcontrol. Complete l l

Trainina & quality Amaranne .

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16. AllDS 7s, Operational Events, wiu be transmitted to the Training Department fbr lessons )

1 Isarned to be included in the training program. CWete l

l 17. QA should evaluate performing a 'pwfonannoe based audit on the adequacy and 1

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J h 'ud Ith 22:39 ID: TEL to sedv P13 4 i 4, l'

L4641 Anahman nests,1996 amhisa I eSpotiveness of the oorporese pmyam hr transhrring lessons learned between Turissy Point and at. Lesis er events widah oesur at du other site, and he events which oseur

! le the industry. Wes Bladow - Due 3/15/96 j Supmislan miW I

18. Operations wlE soview the sumnt watchstanders br Historical Poor Performanos, and aseses need br astion. Complets
19. A Training and Ferdmnance 'Itsview Board wl3 be lasthuted to oceduct a conseEdened review of al perdbananos indicators Air licensed operations personnel wiio are identiSed l

as Missortool Poor Portrasra. The review will amass the used fbr addideaal muodial meneures and/or the rusoval of the Historical Poor Perfbrmer tout licensed dudas.

Compless

20. Plant managense has developed a mushantan fbr providing W on the understanding and * ;' *= of d policies and espectations abr d piant y " 7. (standards Assusmem ouldene by Mrr r) compime l 21. A review wu undertaken to evaluess the adequacy of the adming policy and guidance i

involving ruodvity control. Pima mannsemen wiu now reintros expectations and the

impotense of remedvky contal in a personal letter tom the Plas General Manager and
see Vies Pruident to uch RCO and SRO. Compime L 22. operadas now brisangs by operesions supavision wem held discussing the duution l

ovest, Zach Pate's "The Control Room" and manessment's supostations with respect to L conservative peut opermion. operados supervision also reinemed expectetions in

! conduct of operations wkh rapact to =ia-ia= of opwadoes Manssement, los

Imeping, hous on reesdvhy changes, and the abort term turnover process. Complete i
23. operations Managemsat reviewed its expectations ihr command and control using
labrmados obtained Asa other sites including Turkey Point. De implications of this ovent wit also be reviewed by a team br applicabuity to other operation's assivities both l

laside and outside the control room. J. A. West - STAR 960146B & C - Schedules due 341/96 i

! 24. Nuclear Plant "g i . have been directed to review d new In-House Events at the

! 0740 meeting with Plant Management to help priorities sedvities. Complete

25. In addhion to specisc correesive actions, plant management will self assess the operadon of st. Lucie plant. This self assessment willinclude, but is notlimitad, to Conduct of operations, alarm setpoint poley, opendag experianos indback, training, proomiures, corroodvs nations, and amangemem policies. This review win be partbreed by ping i pareannel sugmsmal by upsienced ladividuals tom otr site. Recommended assions will 11 1

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e- wtl be provided via the Company Nuclear Review Board. Am soucis .

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d March 28, 1996 IA 96-019 Mr. G. H. Holzmacher

[HOME ADDRESS DELETED UNDER10CFR2.790) ,

SUBJECT:

NRC INSPECTION REPORT NO. 50-335/96-03 AND 50-389/96-03

Dear Mr. Holzmacher:

This refers to the special followup inspection at the St. Lucie facility conducted on January 26-30 and February 8, 1996, with regard to a January 22, 1996 Unit 1 overdilution event. The report documenting the NRC inspection is l enclosed. A closed predecisional enforcement conference was conducted in the Region II office on March 8,1996, with Florida Power and Light Company (FPL)  !

J (including you and the other licensed operators involved in the event) to discuss the apparent violations, the root causes, and corrective actions to l preclude recurrence. A copy of the conference summary is enclosed.

Based on the information developed during the inspection and the information i provided during the conference, the NRC has determined that actions taken by you ,

during the January 22, 1996 dilution event involved a violation of NRC requirements. A Notice of Violation and Proposed Imposition of Civil Penalty has been issued separately to FPL for your failure to follow procedures for reactor coolant system boron dilution and your failure to monitor the dilution  ;

evolution conducted on January 22, 1996. This violation involved a serious l lapse of attention on your part to your duties as a licensed reactor operator.

In addition, you conducted an inadequate watch turnover and failed to inform the temporary reitef operator at the controls and the senior reactor operator that a boron dilution was in progress prior to leaving the control room. As a result of these errors, 100 percent reactor power was exceeded on January 22, 1996.

As an NRC Reactor Operator license holder, you are expected to ensure that control room evolutions are conscientiously monitored and that you are actively involved in alant operation. A high level of attentiveness is required in order to fulfill t1ese license responsibilities and thereby ensure protection of the public health and safety. Your actions on January 22, 1996 did not meet these standards. The NRC relies on licensed operators to accurately perform their

. assigned duties. After serious consideration of this matter, we have decided not to take formal enforcement action against you in this case. We recognize that upon realizing your error you took prompt action to correct the mistake and inform the control room staff of the error. In addition, at the predecisional enforcement conference, you indicated that you had learned an important lesson as a result of this event and understood the need to meet your responsibilities as a licensed operator. We expect that as part of your corrective action you will share your lessons learned with other licensed operators at the St. Lucie plant. You should be aware that your performance was unacceptable and if uncorrected, could lead to enforcement sanctions in the future. A CERTIFIED MAIL NO. P 291 242 533 RETURN RECEIPT REQUESTED h- ,

w %.

G] ,._

G.:Holzmacher 2 in accordance with Section 2.790 of the NRC's " Rules of Practice," Part 2, Title 10, Code of Neral Regulations, enforcement actions are placed in the NRC l Public Document Room (PDR). A copy of this letter with your address removed will be placed in the PDR unless you provide sufficient basis to withdraw this action within 30 days.

-No reply to this letter is required; however, should you have any questions or l comments concerning this action, please contact Mr. Thomas A. Peebles, Chief,  !

O mrations Branch. Mr. Peebles can be reached at either the address listed a nve or telephono number (404) 331-5541.

Sincerely, 4

Original Signed by l j- Albert F. Gibson j

j Albert F. Gibson, Director i Division of Reactor Safety Docket No. 6-21934 l l License No. OP-21052

Enclosures:

1. NRC Inspection Report No. 50-335/96-03 and 50-389/96-03
2. Notice of Violation and Proposed Imposition of Civil Penalty to FPL
3. Predecisional Enforcement Conference Summary cc W/HOME f.DDRESS DELETED w/o encls:

, Florida Pc,wer and Light Company ATTN: Mr. T. F. Plunkett President - Nuclear Division ,

P. O. Box 14000 Juno Beach, Florida 33408-0420 Part 55 Docket File

9 s '.

+.

G. Holzmacher '

Di st.ribution WHOME ADDRESS DELETED w/o encls: ,

.Edu'ian, SECY

[ BKeeling, CA JTaylor, ED0 - -

JMilhoan, DEDR i

.SEbneter, RII LChandler, OGC - l 1 JGoldberg, OGC i JLieberman, OE -

Enforcement Coordinators

RI, RIII, RIV-EHayden, OPA >

LTemper, OC i GCaputo, 01 -

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EJordan, AE00  :

-LNorton, OIG ,

OE:EA File (B. Summers, OE) (2)

SRichards, HOLB, NRR ,

JBeall, OE

TPeebles., RII CEvans, RII Buryc, RII KClark, RII RTrojanowski,RI!

CCasto, RII Klandis, RII (IFS Update)

BSchin, RII

. JNorris, NRR

! SHallstros, RII

NUDOCS NRC Resident Inspector

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U.S. Nuclear Regulatory Comm.

7585 South Highway AIA Jensen Beach, FL 34957-2010 cc W/HOME ADDRESS DELETED w/ enc 1:

PUBLIC Part 55 Docket File bM WMS h/artence cron vn mini ne nnettuer annut /vce'l un #

OFFICE Ril:DRS R}:DRP Ril:DRP Ril: $1:DRS Ril:EICS Ril: ORA einNATU Naue Cramo KLand u .f trechs CEvans An han BUrve LReves DATF OS/ . 198 04 / 198 04 / /98 04 / 198 04 / 198 04 / 19e COPY? w/ YES YlM YES YES YES YES _

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RZimmeman,- NRR ,

LChandler, 0GC .

JGoldberg, 0GC. j Enforcement Coordinators j RI, RII, RIII; RIV  ;

FIngram,.OPA.  !

DWi'liams, DIG.  !

GCaputo, 01 i LTrooper, DC .!

i EJordan, AE00 J8eall, OE -

~ DE:EA File (2) l NUDOCS H. Christensen, RII.  !

N. Le, NRR  !

G. Ha11strom, RII  ;

PUBLIC-NRC Resident Inspector l U. S. Nuclear Regulatory Consission  !

j 5421 Shearon Harris Road

- New Hill, NC 27562-9998 F

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From: -- Linda Watson To: ATb, ARL, BXU .

Date: 3/28/9611:24am .

Subject:

St. Lucie IA No.-

I got the IA number (IA 96-019) for the operator involved in the ST. Lucie dilution issue and put it in the package. Both documents are sdll in Ebneter's omce. Hellan said she.

mentioned them to him before Current Events. I have revised the letten to include date -

and " signed by" notes and a printout is on my desk for the Anal venion. When I called Dawn, she indicated we needed an EA number for the operator. This is not what Joe Gray ,

. said last week. He indicated no EA number would be used. Only the IA number. Dawn will call us if a separate EA number is pulled for the operator.

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.U.S. Nuclear Regulatory Commission 1 101 Mari tta St., N.W.

Suite 2900

[

l Atlanta, GA 30323

No: 11 96 36 .

FOR IMMEDIATE RELEASE <

i

Contact:

Ken Clark (404) 331-55J3 (Friday, March 29, 1996) p Roger Hannah (404) 331-7878 ,

2- NRC STAFF PROPOSES $50,000 CIVIL-PENALTY j AGAINST ST. LUCIE NUCLEAR POWER PLANT j

. The Nuclear Regulatory Commission staff has proposed a $50,000 civil penalty against Florida Power ' & Light Company' for alleged violation of NRC safety 1

requirements at'the St. Lucie nuclear power plant, located on Hutchinson Island 'j near Ft. Pierce, Florida. l NRC officials said the fine is being proposed because a Unit 1 control room I

. operator on January 22, 1996 failed to follow procedures for diluting the boron

concentration in the reactor coolant system, causing reactor power to rise above authorized limits for.a short period of time, p Boron is used in reactors to absorb neutrons and help control the fission
process. As reactor fuel ages, boron concentrations are diluted to help maintain

! operating zwer levels.

The hRC said the operator was diluting reactor coolant in a procedure

. requiring the addition of from 25 to 40 gallons of water which should have taken i less than a minute to perform. Instead, the operator and other crew members conducted an inadequate watch turnover during which a temporary relief operator

! and the senior reactor operator were unaware that a boron dilution was in progress. This'resulted in an unplanned reactivity increase since the operator failed to stop the addition of primary makeup water until approximately 400 gallons were added.

! NRC officials said the actual safety consequences of the event were low

' because the operator recognized the error, and the crew took prompt actions to

. restore plant parameters. However, they said the event demonstrated operator performance problems because (1) the method routinely used by St. Lucie oprators to dilute reactor coolant was not authorized by procedures: (2) the metnod used j was not as described in an updated plant Final Safety Analysis Report; (3) operators routinely performed the dilution procedure from memory instead of referring to written procedures as required; and (4) operators failed to give

prompt verbal notification to the Operations Supervisor that an unplanned
reactivity c1ange had occurred.

r The company has 30 days from receipt of the Notice of Violation to either pay the fine or to protest its imposition.

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