IR 05000387/1985030

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Enforcement Conference Repts 50-387/85-30 & 50-388/85-25 on 851001.Major Areas Discussed:Licensee Ability to Safely Shut Down Plant in Event of Fire & Violations Identified in Insp Repts 50-387/85-06 & 50-388/85-06
ML17139D308
Person / Time
Site: Susquehanna  Talen Energy icon.png
Issue date: 11/01/1985
From: Anderson C, Krasopoulos A
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML17139D307 List:
References
50-387-85-30, 50-388-85-25, NUDOCS 8512100583
Download: ML17139D308 (28)


Text

U.S.

NUCLEAR REGULATORY COMMISSION

REGION I

Meeting Nos.

50-387/85-30 50-388/85-25 Docket Nos.

50-387 50-388 License Nos.

NPF-14 and NPF-22 Priority Licensee:

Penns lvania Power & Li ht Com an 2 North Ninth Street Allentown Penn s 1 vani a 18101 Category C

Facility Name:

Sus uehanna Steam Electric Station Unit 1 and

Meeting at:

USNRC Re ion

Kin of Prussia Penns lvania Meeting conducted:

October

1985 vaja Prepared By:

a.

A.

G.

ra sopou 1 o s, Reactor Engineer

]~ (

$'S date Approved by:

C.

. Anderson, Chief Plant Systems Section, DRS date M~i:

E f

NR i

I

b 1,

to discuss the findings identified in the combined Inspection Report Nos.

50-387/85-06 and 50-388/85-06, which reviewed the licensee's ability to safely shutdown the plant in the event of a fire.

The items discussed were the two violations identified in the report and various commitments made to NRC in a meeting held in Bethesda, Maryland on April 18, 1985 concerning the findings of the above inspection.

The licensee presented the NRC concerns and their positions on these issues as well as commitments made that would satisfy these concerns.

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DETAILS Partici ants Penns lvania Power and Li ht Co.

PP&L W. Barberich C. Coddington H. Keiser D.

Kohn A. Male D.

McGann D. Thompson Manager, Nuclear Licensing Senior Project Engineer, Licensing Vice President, Nuclear Operations Fire Protection Engineer Manager, Nuclear Design Compliance Engineer Assistant Plant Superintendent 1.2 Nucl ear Re ul ator Commi ssi on NRC J. Allan C. Anderson W. Butler M. Campagnone J. Durr S.

Ebneter R. Ferguson R. Fuhrmeister J. Gutierrez D. Holody A. Krasopoulos T. Murley T. Poindexter S. Pullani J. Strosnider Deputy Regional Administrator Chief, Plant System Section Chief, L.B. No.

Project Manager, NRR L.B. No.

Chief, Engineering Branch Director, Division of Reactor Safety Section Leader Reactor Engineer Regional Counsel Enforcement Specialist Reactor Engineer Regional Administrator Enforcement Staff Lead Reactor Engineer Section Chief, DRP 2.0 3.0

~Put ose The enforcement conference was held at the request of NRC Region I, to discuss the findings of the inspection conducted to assess the licensee's compliance with the requirements of 10 CFR 50, Appendix R.

Presentation and Discussion NRC Region I Regional Administrator, Dr. T. Murley opened the conference by asking the licensee to present their perspective on the findings'ollowing an introduction of the participants, the NRC Region I Director of the Division of Reactor Safety, Mr. S.

Ebneter stated the purpose of the meeting and iterated the sequence of events leading to the enforcement conference.

Mr. H. Kaiser, Vice President of Nuclear Operations of PP&L responded to the NRC*concerns by first addressing the violations identified in the report and then responding to various Appendix R concern A discussion followed on what constituted a fire barrier and a degraded fire door.

Subsequent to the discussion of the violations, the licensee presented their plan to resolve the Appendix R issues.

The licensee committed to reanalyze the fire zones, redefine fire areas, and upgrade fire barriers as necessary by installing penetration seals, fire dampers, and rated doors.

They also committed to review unrated fire zone boundaries, make an associate circuit analysis for fire zones outside and within the Control Room, and identify exemptions to Appendix RE The licensee also committed to dates when the installation and analysis would be complete.

(See attachment 1, licensee's presentation material)

4.0 Concludin Statements The Regional Administrator and the Director of the Division of Reactor Safety thanked the licensee for their presentation and stated that this information would be considered in the NRC's determination of enforcement actions related to these issue ATTACHMENT 1 Licensees Presentation Material AGENDA

INTRODUCTION PART I FIRE PROTECTION ISSUES

STATUS OF CORRECTIVE ACTION AND SCHEDULE FOR COMPLETION FOR VIOLATIONS TRANSMITTED IN INSPECTION REPORT 50-387/85M AND 50-388/85M

INADEQUATE TESTING OF FIRE DAMPERS

NON-FUNCTIONAL FIRE DOORS

STATUS OF CORRECTIVE ACTIONS AND Cot%ITMENTS MADE DURING MEETINGS WITH NRR

PLANNED ACTIONS/SCHEDULE FOR COMPLETION OF THE FOLLOWING ITEMS o

85-06-07 o

85-06-04 o

85-06-05 PART II HISTORICAL PERSPECTIVE

PLANNED ACTIONS FOR THE FOLLOWING ITEMS o

85-06-02 o

85-06-01

CONCLUSION

i wf

ITEMS 50-387/85-06-10 AND 50-388/85-06-10 INADEQUATE TESTING OF F IRE DANPERS NRC CONCERN

CERTAIN FIRE DAMPERS WERE NOT FUNCTIONALLY TESTED PER THE REQUIREMENTS OF THE NDICA-15,3,1 PP8L POSITION

THIS ITEM IS NOT A VIOLATION

No REGULATORY REQUIREMENT To FUNCTIONALLY TEST DAMPERS

SECTION 6<3 OF THE NDI ONLY APPLIES TO ACCEPTANCE TESTING,

IN ACCORDANCE WITH SECTION 6s4 OF THE NDI p SPECIFIES TESTING IS DONE ON A REGULARLY SCHEDULED BASIS; 1,

SEGTIQN 6<4 QF THE NDI DoEs NOT REFERENcE NFPA.

2, TESTING AND SURVEILLANCE IS PER THE TECHNICAL SPECIFICATIONS WHICH SPECIFY VISUAL INSPECTION

IN ACCORDANCE WITH NFPA-90Ai APPENDIX Bp SECTION B-7i FUNCTIONAL TESTING IS OPTIONAL CONC( USIoN

VISUAL SURVEILLANCE OF DAMPERS IS TECHNICALLY ADEQUATE AND COMPL IES WITH REGULATORY REQUIREMENTS

ITEM 50-%7/85-06-11 NON-FUNCTIONAL FIRE DOORS NRC CONCERN

CERTAIN FIRE DOORS NOT NAINTAINED AS FIRE BARRIERS

CERTAIN FIRE DOORS WERE NON-FUNCTIONAL PPaL REsPONsE

THIS ITEM IS NOT A VIOLATION

NON-FUNCTIONAL FIRE DOORS SPECIFIC PROBLEMS:

BROKEN.DOOR LATCH AND CLOSER NECHANISM DOORS HELD OPEN REPAIRED BY PLANT NAINTENANCE NUMBER OF NON-FUNCTIONAL DOORS NOT EXCESSIVE

FUSIBLE LINKS APPROVED AS PART OF FPRR AND FSAR NO NFPA OR NRC STANDARD PROHIBITS FUSIBLE LINKS NO TECHNICAL CONCERNS WITH RE USE OF FUSIBLE LINKS

~ ~

NRC CONITKNTS

REVIEW THE UNRATED FIRE ZONE BOUNDARIES

ANALYZE THE ASSOCIATED CIRCUITS WITHIN FIRE ZONES OUTSIDE THE CONTROL ROOM

IDENTIFY ANY EXEMPTIONS TO APPENDIX R SECTION III,G

ANALYZE THE ASSOCIATED CIRCUITS WI'THIN THE CONTROL ROOM

NRR CONITttENTS UNRATED FIRE ZONE BOUNDARIES

COl%ITMENT

REANALYZE FIRE ZONES

RE-DEFINE FIRE AREAS PER APPENDIX Ri III,G,

UPGRADE BARRIERS AS REQUIRED

STATUS

ANALYSIS COMPLETE (PLA-2529, SEPT, 4, 1985)

UPGRADE BARRIERS OR PORTIONS OF BARRIERS

RATING OF FIRE DOORS (NO PHYSICAL REPLACEMENT)

INSTALLATION OF FIRE DAMPERS

INSTALLATION OF SEALANT TO PENETRATIONS (

10/o HAD TO BE INSTALLED)

FIVE EXEMPTION REQUESTS WERE REQUESTED

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CRITERIA FOR FIRE PROTECTION OF SAFE SHUTDOWN SYSTPS WITHIN A FIRE ZONE WHICH DO NOT CONPLY WITH THE REQUIRPENTS OF SECTION III,G

CeeImENT

IDENTIFY THE SPECIFIC FPRR SECTION 2,11 CRITERIA FOR EACH FIRE ZONE

'

PROVIDE EXEMPTION REQUESTS AND JUSTIFICATION

STATUS

REPORT SCHEDULED TO BE COMPLETED NOVEMBER 15 1985

THE ANALYSIS OF ASSOCIATED CIRCUITS. WITHIN THE CONTROL ROON

COMMITMENT

REANAI YZE THE EFFECTS OF A FIRE IN THE CONTROL ROOM ON THE ABILITYTO SHUTIXMN

ALTERNATE SHUTIXNN SYSTEMS AND THEIR SUPPORT SYSTEMS WILL REMAIN OPERABLE FROM OUTSIDE THE CONTROL ROON

NO SINGLE SPURIOUS SIGNAL WILL AFFECT ABILITYOF ALTERNATE SHUTDOWN SYSTEMS TO FUNCTION

NO SPURIOUS SIGNAL WILL CAUSE LOSS OF INVENTORY

STATUS

.

ANALYSIS COMPLETED PLA-2529>

SEPTEMBER 4> 1985

ONE ADDITIONAL PERMANENT NANUAL ACTION NOT ALREADY COVERED BY PROCEDURE IS NECESSARY TO PREVENT HIGH/LOW PRESSURE INTERFACE CAUSED BY THE SPURIOUS ACTUATION OF BOTH REACTOR HEAD VENT VALVES ON EACH UNIT

INITIATIONOF INTERIM PROCEDURES (24 FANS)

EXEMPTION REQUEST PROCEDURE TO START BATTERY ROON EXHAUST FANS BE ADOPTED AS PERMANENT CORRECTIVE ACTION

THE ANALYSIS OF ASSOCIATED CIRCUITS WITHIN FIRE ZONES OUTSIDE THE CONTROL ROON

COMMITMENT

VERIFY SUCCESSFUL OPERATION OF NINORITY DIVISION SAFE SHUTDCW SYSTEM OR SUPPORT SYSTEM CAN NOT BE DEFEATED BY A SPURIOUS SIGNAL FROM NAJORITY DIVISION AND THAT MINORITY DIVISION SYSTEM OPERATION DOES NOT RELY ON A NAJORITY DIVISION COMPONENT

VERIFY VESSEL INVENTORY IS NOT COMPROMISED BY SPURIOUS OPERATION OF A NAJORITY DIVISION COMPONENT

STATUS,

ANALYSIS SCHEDULED TO BE COMPLETED - NOVEMBER 15'985

ITEM 50-%8/85-06-07 EYERGENCY LIGHTING BATtERY POWER SUPPLY NOT 8-HOUR RATED IN FIRE ZONE 2-2A NRC CONCERN

ONE EMERGENCY LIGHTING BATTERY POWER SUPPLY NOT IN ACCORDANCE WITH SECTION III,J OF APPENDIX R, PPRL RESPONSE

THIS IS A VIOLATION

NON-CONFORMING BATTERY POWER SUPPLY WAS REPLACED ON JULY 19'985,

THIS DOES NOT CONSTITUTE A SAFETY CONCERN SINCE THE PATH LIT BY THIS POWER SUPPLY WOULD BE USED MINUTES AFTER A FIRE STARTED IN THE CONTROL ROOM,

ITEM 50-388/85-06-04 LACK OF AUTONTIC SUPPRESSION IN EQUIPNENT RPDVAL AREA AND EQUIPttlENT SHAFT AREA NRC CONCERN 0,

AUTOMATIC SUPPRESSION HAS NOT BEEN INSTALLED IN FIRE ZONES 2-3B AND 2-5A PER THE FIRE PROTECTION PROGRAM PAL REsPoNsE

THIS IS NOT A VIOLATION

FIRE ZONE 2-3B FIGURE 5,10 CORRECTLY SHOWS PARTIAL AUTOMATIC SUPPRESSION INSTALLED, AUTOMATIC SUPPRESSION INSTALLED IN ACCORDANCE WITH F IRE PROTECTION PROGRAM REQUIREMENTS

FIRE ZONE 2-5A FIGURE 5,12 INCORRECTLY SHOWS AUTOMATIC SUPPRESSION CONFIGURATION NO NEED FOR AUTOMATIC SUPPRESSION IN FIRE ZONE

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IT~ 50-%8/85-06-05 INGNPLETE ONE HOUR FIRE BARRIERS IN FIRE ZONE 2-4A NRC CONCERN IN FIRE ZONE 2-4Ai THE INSTALLATIONOF FIRE BARRIERS DID NOT PROVIDE THE REQUIRED ONE HOUR SEPARATION/PROTECTION, PPRL RESPONSE

THIS IS NOT A VIOLATION

WRAPPING IS NOT WALL TO WALL

ONE HOUR INSTALLED WRAPPING SATISFIES THE CRITERIA OF SECTION 2,11 OF THE FPRR IN THAT WRAPPING EXTENDS AT LEAST 50 FEET FROM REDUNDANT CABLES,

THIS IS AN EXEMPTION TO APPENDIX R WHICH WILL BE SUBMITTED ON 11/15/85 IN ACCORDANCE WITH THE CueImENTS NeE TO NRR,

INSTALLATIONAT INTERFACE OF BARRIER AND WALL,

ONE HOUR WRAPPING IS INSTALLED IN THE CONFIGURATION OF THE AUGUST 1982 TEST WHICH SHONED THAT THE WRAP PROVIDED ONE HOUR PROTECTION TO THE CABLES AT THE INTERFACE POINT,

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INTERFACE 1 HR.

REF. PP(.L TEST AUG. I98Z 5 HR. SILICONE PENETRATION SEAL i~.TSI THERMAL LAG 1 HR.

REF. T.S.I. TEST ET.L. 82.-ll-80 WALL

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ITEMS 50-387/85-06-01 AND 50-388/85-06-01 FIRE HAZARD ANALYSIS - INADEQUATE TO SHOW APPENDIX R IS SATISFIED ITEMS 50-387/85-06-02 AND 50-388/85-06-02 LACK OF SEPARATION IN RHR PUMP ROOMS NRC CONCERN

ANALYSIS NOT BASED ON FIRE AREA CONCEPT

ADEQUACY OF FIRE ZONE BOUNDARIES

LIMITED FIRE ASSUMED

ANALYSIS SHOWS CONFORMANCE TO BTP APCSB 9,5-1 NOT APPENDIX R Pal RESPONSE

THIS IS NOT A VIOLATION

THE PAL ZONE CONCEPT IS EQUIVALENT TO AREA CONCEPT IN THAT FIRE IS CONTAINED WITHIN THE ZONE

BOUNDARY RATINGS WERE PREVIOUSLY ACCEPTED

45 MINUTE EQUIVALENT FIRE SEVERITY

6ENERIC LETTER 83-33 ENDORSES APPROACH

LIMITED FIRE WAS NOT ASSUMED

TRANSIENT AND IN SITU COMBUSTIBLES WERE CONSIDERED TO BE CONSUMED

NOMINAL 45 MINUTE BARRIER DESIGN WAS NOT EXCEEDED WITH 15 MINUTE TRANSIENT LOADING ADDED

PAL SOUGHT AND RECEIVED APPROVAL OF PROGRAM REVIEW WAS BASED ON APPENDIX R AS INTERPRETED BY STAFF AT TIME,

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APPROVAL PROCESS BTP APCSB 9,5-1 (APPENDIX A) ISSUED BY NRC (FEBi 77)

SSES FIRE PROTECTION REVIEW REPORT (FPRR)

ISSUED (JANi 78)

NRC PROPOSED RULE 10 CFR 50,48 AND APP, R PUBLISHED FOR C9%ENT (NAY 80)

NRC SITE WALKIKWN ON FIRE PROTECTION (OCT/NOVi 80)

NRC rssuED 10 CFR 50.48 AND APPENDrx R (Nov, 80)-

NRC ISSUED 40 AND 281 SERIES QUESTIONS (FIRE PROTECTION)

TO SSES (JAN, 81)

PAL RESPONDED TO NRC QUESTIONS (FEBi 81)

REvrsroN 1 To SSES FPRR rssuED (Nm, 81)

PP8L/NRC MEETING (MAR, 81)

PAL C(MITTED TO III,Gi J 8, 0,(DOCUMENTED IN PLA-683)

NRC IssuED NUREG 0776 (SSES SER)

(Ar R, 81)

NRC ISSUED SUPPL, ¹1 To SSES SER (JUNi 81)

NRC rssuED SUPPL, ¹2 To SSES SER (SEP, 81)

PAL COMPLETED REMOTE SHUTDOWN NODIFICATION (DECi 81)

PAL REQUESTED VARIANCE FOR USE OF 1-HOUR WRAP (FEBi 82)

.

NRC IssUED SUPPL, ¹3 To SSES SER (JuL, 82)-

UNIT 1 OPERATING LICENSE ISSUED (JULi 82)

PP8L ceerTTED To morn 1-HouR WRAP (AuG, 82)

PPRL COMPLETED WRAP NODIFICATION (OCTi 82)

NRC ISSUED SUPPL, ¹4 To SSES SER (NOVi 82)

REYIsIQN 2 To SSES FPRR IssuED (DEc, 82)

PAL REQUESTED LICENSE AMENDMENT TO INCORPORATE REV, 2 To FPRR (JANi 83)

NRC IssuED SUPPL, ¹5 To SSES SER (NARi 83)

AMENDMENT 16 To'UNIT 1 LICENSE ISSUED To INCORPORATE REV, 2 TO THE SSES FPRR (SEP, 83)

NRC ISSUED GENERIC LETTER 83-33 (OCTi 83)

PAL REQUESTED EXEMPTION FROM APP R SEPARATION CRITERIA (DECi 83)

NRC IssuED SuPPL, ¹6 TO SSES SER (OR, 84)

UNIT 2 OPERATING LICENSE ISSUED (NARi 84)

CONCLUSION

PAL'S FIRE PROTECTION PROGRAM

ADEQUATE TO PROTECT THE PLANT

NANAGEMENT ATIENTION IS EVIDENT

SATISFIES THE INTENT OF APPENDIX R

INSPECTION ITEMS

ONLY ONE ITEM IS CONSIDERED A VIOLATION AND IT HAS NO SAFETY SIGNIFICANCE

THE SCHEDULE TO CLOSE UNRESOLVED ITEMS EXISTS AND IS TIMELY

SSES FIRE PROTECTION LCO'S UNIT 1 LCO'S, INCURRED WHICH REQUIRED FIRE WATCHES IN 1985:

JANUARY FEBRUARY MARCH APRIL 102

22

16 JUNE JULY

21 AUGUST SEPTEMBER STATUS AS OF 9/23/85:

UNIT 1 ONLY LCO's

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LCO's CURRENTLY IN FORCE

SSES FIRE PROTECTION LCO'S UNIT 2 LCO's INCURRED WHICH REQUIRED FIRE WATCHES IN 1985:

JANUARY FEBRUARY MARCH APRIL

15 JUNE JULY

14 AUGUST SEPTEMBER STATUS AS OF 9/23/85:

'UNIT 2 ONLY LCO's COMMON UNIT LCOss

16 LCO's CURRENTLY IN FORCE

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