IR 05000289/1986098

SALP Rept 50-289/86-98 for Nov 1986 - Oct 1987

ML20196D863
Person / Time
Site:	Three Mile Island
Issue date:	02/11/1988
From:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20149J223	List: IR 05000289/1986098 ML20149J219
References
50-289-86-98, NUDOCS 8802220326
Download: ML20196D863 (65)

Text

<

,

<.

?

ENCLOSURE 4 U. S. NUCLEAR REGULATORY CCMMISSION

REGION I

SYSTEMATIC ASSESSMENT OF LICENSEE PERFORVANCE 50-239/S6-93 (AMENDED REPORT)

GPU NUCLEAR THREE MILE ISLAND, UNIT 1 NOVEMBER 1, 1956 - OCT03ER 31, 1937

-

1. , %x

/@g230BN- (f

._ _ _ _ - _ _ _ _ _ _ _ _ _ - _ _ _

,

,

.

• SUMMARY ACTUAL PERCENT 1. PLANT OPERATIONS 1433 29 2. RADIOLO3ICAL CONTROLS 246 5 3. MAINTENANCE 424 9 4. SURVEILLANCE 465 9 5. FIRE PROTECTION 440 9 6. EMERCENCY PREPAREDNESS 373 7 7. SECURITY AND SAFEGUARDS 194 4 8. OUTAGES 419 8 9. LICENSIN3 ACTIVITIES N/A N/A 10. ENGINEERING SUPPORT 972 20 11. TRAINING AND QUALIFICATION N/A N/A EFFECTIVENESS 12. ASSURANCE OF QUALITY N/A N/A

!

-

TOTALS 4966 100 l

!

T-2-1

.

'

o

• ,

,

TABLE 3 ENFORCEMENT SUMMARY A. Violations Versus Functional Area by Severity Level SEVERITY LEVEL FUNCTIONAL AREA V IV _Ill 11 1 TOTAL PLANT OPERATIONS 0 RADIOLOGICAL CONTROLS 1 1 MAINTENANCE 1 1 SURVEILLANCE 1 1 FIRE PROTECf10N 1 1 EMERGENCY PREPAREDNESS 1 1 SECURITY / SAFEGUARDS 0 OUTAGES 1 1 LICENSIN3 ACTIVITY 0 ENGINEERING SUPPORT 3 3 T&Q EFFECTIVENESS 0 QUALITY ASSURANCE 1 1

_ _ . _ . _ _ _ _

TOTALS 1 9 3 0 0 10 l

I T-3-1 i

.

-

,

t

,

Table 3

. Violation Summary INSPECTION SEVERITY FUNCTIONAL REPORT /DATE REQUIREMENT LEVEL AREA BRIEF DESCRIPTION 289/86-23 10 CFR 50 5 FIRE PROT./ FAILURE TO INSTALL EMERGENCY AFP R SEC.III ENG. SUP LIGHTS IN THE CONTROL ROOM 259/86-24 10 CFR 50 4 EN^ SUP FAILURE TO TAKE TIMELY AND ADE-APP B QUATE CORRECTIVE ACTION ON CRIT. XVI ENVIRONVENTAL QUALIFICATION (EQ)

PROGRAN DEFICIENCIES 289/87-01 10 CFR 50 4 OUTAGE /EN FAILURE TO FOLLOW VENDOR IN-APP B SUP STRUCTIONS FOR SEISMIC MOUNTING CRIT. V 0F RCS PRESSURE INSTRUMENTATION 259/37-06 10 CFR 50 4 ENG. CUP FAILURE TO DESIGN REVIEW AND APP B APPROVE AN HSPS CALCULATION SY CRIT. III VENDOR 259/57-06 TS 6. SURVEILLANCE FAILURE TO PROPERLY FOLLOW CAL)-

BRATION PROCEDURE FOR REACTOR BUILDING PRESSURE INSTRUMENTATION 259.'57-08 10 CFR 50.598 4 ASSURANCE OF FAILURE TO PRODERLY DO:UMENT QUALITY SAFETY REVIEWS 289/87-09 10 CFR 20.201 4 RAD-CHEM FAILURE TO SURVEY FOR WORK IN (B) LETDOWN PREFILTER CUBICLE 289/87-09 10 CCR 50 4 ENG. SUP FAILURE TO ADEQUATELY DESIGN A?P B REVIEW PRESSURIZER INSULATION CPIT. III SUPPORT PLATFORM 239/57-14 10 CFR 50 4 EMERG. PREP. FAILURE TO PROPERLY CLASSIFY AND AFP E AND SEND TO NRC AN EMERGENCY ITEM 5 PLAN IMPLEMENTING PROCEDURE 289/87-19 TS 6. MAINTENANCE FAILURE TO FOLLOW PROCEDURE CN LIFTED LEAD AND INDEPENDENT VERIFICATION T-3-?

.

'

>

t o

.

TABLE 4 QENSEEEVENTREPORTS LER By Functional Area NUMBER BY CAUSE CODE FUNCTIONAL AREA A B C D E TOTAL PLANT OPERATIONS 3 1 4 RADIOLO3ICAL CONTROLS 0 MAINTENANCE O SURVEILLANCE 2 1 3 FIRE PROTECIION 0 EMERGENCY PREPARE 0 NESS 0 SECURITY AND SAFEGUARDS 0 OUTAGES 1* 1* 1* 3 LICENSING ACTIVITIES 0 ENGINEERING SUPPORT 0 TRAINING AND QUALIFICATION 0 EFFECTIVENESS ASSURANCE OF QUALITY 0

_ _ _.__ _ _ _

S 6 1 0 2 1 10

• Involves other functional areas, but event occurred during outage activitie Cause Codes A - Personnel Error 8 - Design, Manufacture, Fabrication C - External D - Procedure Inadequacy E - Component Failure / Malfunction T-4-1

--

-

.

,

! Table 4

. ER SYNOPSIS FUNCTIONAL CAUSE LER NUv3ER SUMvARY AREA _ CODE 86-13 REACTOR BUILDING LEAK TEST FAILED DUE SURVEILLANCE / D TO PENETRATION PRESSURE VALVE LEAKAGE ENG. SUPPORT NOT DETECTED DURING PREVIOUS LOCAL LEAK RATE TESTS 87-01 AUTO START OF A DIESEL DUE TO DEFEC- OUTAGE (MODIFI- D TIVE WORK INSTRUCTION ICATION)/EN SUPPORT 87-02 DIESEL GENERATOR AUTO START DURING OUTAGE B ADJUSTMENT OF RELAY COVER DUE TO IM- (MAINTENANCE)

?ROPERLY "CRESSED" WIRING WHICH DID NOT ALLOW FOR COMPLETE FIT OF RELAY COVER 87-03 FIRE BARRIER PENETRATION SEAL NOT IN- OUTAGE (FIRE A CTALLED DUE TO ENGINEERING SUPPORT PER- PROTECTION -

SONNEL OVERSIGHT SURVEILLANCE)

87-04 REACf0R TRIP ON HIGH PRESSURE DUE TO SURVEILLANCE A OPERATOR FAILURE TO VERIFY ACTION DURING HEAT BALANCE SURVEILLANCE 87-05 MISSED SAMPLE PRIOR TO INDUSTRIAL WASTE OPERATIONS A FILTERING SYSTEM RELEASE DUE TO FAILURE TO FOL!OW PROCEDURES 87-06 REACTOR TRIP ON HIGH RCS PRESSURE DUE OPERATIONS A TO OPERATOR ERROR ON MANUAL FEEDWATER CONTROL DURING LCW POWER OPERATIONS 87-07 INADVERTENT REACTOR PROTECTION SYSTEM OPERATIONS A ACTUATION DUE TO COGNITIVE ERROR IN PERSONNEL NOT READING THE MOST CON-SERVATIVE PRESSURE INSTRUMENT WHEN COMING OUT OF SHUTDOWN BYPASS 87-03 REACTOR TRIP FROM TURBINE TRIP DUE TO OPERATIONS E EQUIPMENT MALFUNCTION IN A MOISTURE SEPARATOR LEVEL CONTROL VALVE 87-09 EFFLUENf RADIATION MONITOR INTERLOCK SURVC.I L LANCE A DEFEATED DURING RF. LEASE DUE TO FAILING TO FOLLOW PROCEDURES T-4-2

,

&

.

ENCLOSURE 5 SALP BOARD REPORT ERRATA SHEET PAGE LINE NOW READS SH_0ULD READ 17 9-11 Site and corporate management appeared ...to initial radio-somewhat inattentive to the radiologi- logical control prob-cal control pr oblems in the letdown lems... Subsequent filter cubicle, attention has resulted in proper performanc Basis: Statements in licensee's letter and inspector observations that no further problems resulte PAGE LINE NOW READS SHOULD READ 36 35-38 Since that time, the licensee has Since that time, the changed course repeatedly, preferring licensee has changed a less conservative approach and course, opting to pur-causing delays in re>olving the fire sue demonstration of protection issue, adequacy by analysis rather than making hardware change This has caused delays in resolving the fire protection issu Basis: It is premature for the NRC to conclude the licensee's action is less con-servative, since the review is still in progres PAGE LINE NOW READS SHOULD READ 37 17-23 Other licensing issues which could Another licensing issue have been dealt witn better were:

,

that could have been '

(1) the reorganization of the Radio- dealt with better was logical Controls Department, which the reorganization of required repeated submittals to cor- the Radiological Con-rect minor oversights; and, (2) the trols Department, which chlorine detection system technical required repeated sub-specifications for which inadequate

,

mittals to correct i justification was proposed to meet minor oversight This RG 1.95. These delays... delay appears...

Basis: The statement was incorrect because GPUN had never committed that the chlorine monitor would meet the provisions of RG 1.9 I l

_ _ _ . _ _ _ _ _ _

o

.

Enclosure 5 2 PAGE LINE NDW READS SHOULD READ 40 3-5 As as additional exemple, the reactor Omit sentence, water level design has a single fail-ure susceptibility, apparently to alleviate concerns for too many instru-ments in the control roo Basis: To date, the NRC has not concluded the single failure of the reactor water level design is unacceptabl PAGE LINE NOW READS SHOULD READ 40 40 ... additional testing of quality ... additional evalu-materials... ation of quality mate-rial s. .

Basis: Additional testing was not required, only some additional evaluation.

l l

i l

l l

l l

l l

.

l

,

,