IR 05000312/1986029

SALP Rept 50-312/86-29 for June 1985 - June 1986

ML20214K973
Person / Time
Site:	Rancho Seco
Issue date:	08/12/1986
From:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
To:
Shared Package
ML20214K964	List: IR 05000312/1986029 ML20214K961
References
50-312-86-29, NUDOCS 8612020532
Download: ML20214K973 (55)

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. S. NUCLEAR REGULATORY C0fetISSION-i; REGION V

. J SYSTEMATIC ASSESSMENT OF LICENSEE PERFORMANCE FOR SACRACMENTO MUNICIPAL UTILITY DISTRICT RANCHO SEC0 NUCLEAR GENERATING STATION

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l REPORT NO. 50-312/86-29 EVALUATION PERIOD: 06/01/85- 06/30/86

. ASSESSMENT CONOUCTED

AUGUST 12, 1986

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8612020532 861114 PDR ADOCK 05000312 o PDR I

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SUMMARY (06/01/85-06/30/86)

Inspections' Conducted Enforcement Items Insp.** Percent Severity Level ***-

Function Area Hours of Effort I II III IV V Dev. Pend * ' Plant Operations 2468 46 1 1 1 8 Radiological 317 6 2 1 4 7 Controls . Maintenance 211 4 1 1 Surveillance - 287 5 1 ' Fire Protection . 184 3 Emergency-Preparedness 260 5 5

' Security and

> Safeguards 545 10 2 1

' Outages -'

324 6 QualityProgr$ms/ 531 10 1 2 1 1 Administrative 1 Licensing Activities NA NA 1 Training -

33 1 1 Engineering and Construction 192 4 1 1 1 Totals 5352 100 0 0 3 7 5 6 23

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• Pending final escalated enforcement actio ** Allocations of inspection hours vs. functional areas are approximations based upon inspection report data, and include onsite and in-office inspection effort. Does not include PAT /IE inspection hours or SALP preparation hours.

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• • • Severity levels are in accordance with NRC Enforcement Policy. (10 CFR Part 2, Appendix C).

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Data compiled from Inspection Report Nos. 85-16 through 86-23, excluding 85-23,

. covering inspections performed during the assessment period 06/01/85 - 06/30/8 .

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TABLE 2

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Rancho Seco Enforcement Items 06/01/85 - 06/31/86 (85-19 through 86-23)

Inspection Severity Functional Report N Subjec Leve Area 85-19 Failure to establish design _and III 9 installation control measures to ensure integrity of nitrogen supply and vent header syste Failure to provide: adequate lighting IV- 7 level Failure to follow radiation procedures V 2 for carrying pocket dosimeter and dressing in' protective-clothing in controlled area >

Failure to comply with technical speci- IV -2 fication required verification of flow rates during calibration of stack radiation monitor Failure to provide PASS. system training D 2 at committed frequenc Failure to provide committed schedule for D 2 design / procurement of PASS sample shields'.

Fa'ilure to provide committed PASS proce- D 2

.., dures for recovery of particulate and iodine media under'high sample activity condition Failure to complete committed PASS remote D 2 adjustment capability for water / nitrogen

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i, manifold and ion chromatograp .,

85'-29 . Failure to adequately search hand-carried III 7

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package.

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85-30 Failure to provide approved procedure for V 4

, calibration.of power range instrument (gain adjustment).

Failure to comply with Technical Specifi- IV 1 cation cooldown rate of 100*F/hr during October 2, 1985 transien h y? ~ ~ ~

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.b TABLE 2 (continued)

. ' Rancho Seco Enforcement Items

.06/01/85 --06/31/86 (85-19 through 86-23)

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.. Inspection Severity Functional

- Report N Subject Level Area 1n '85-34 Failure to follow access control procedure (a) 7 86-04- Failure'to annotate computer printout (b) 7 regarding alarm response and assessmen i Degraded vital: area barrie (b) 7 Security officer found asleep in' degraded .( b)' 7 vital area barrier compensatory pos Compensatory measures failure _ (b) 7 Failure-to properly escort' visitors an (b) 7 tailgating into vital areas ~.

[- _ Failure to search vehicl (b) 7 86-05 Failure to perform 10 CFR 50.59 safety IV 2 review.of new building constructed and

% - u' sed to process radwast Failure to fol' low procedures to make

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-86-0 P 6

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- in-plant announcements and provide complete. initial notification information-to localJgovernment agencies.

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' Failure to follow procedures to make P 6

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follow-sp notifications to local govern-ment-agencie Failure to maintain emergency plan P 2

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implementing procedure with current radiation monitor setpoint '

Failure to implement emergency and P 2

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annunciator. procedure requirements to obtain samples, and evacuate the

. auxiliary building and wear respirator (a) This violation was combined with the violation in inspection report 85-29 in the aggregate as a Severity Level III proble (b) All 86-04 violations.were listed in the aggregate as a Severity Level III proble u

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' TABLE 2 (continued)

, Rancho'Seco Enforcement. Items 06/01/85 - 06/31/86 (85-19 through 86-23)

Inspection- Severity Functional Report N . Subject Level Area 86-07 Improper. termination of cable shield wir D 12 Failure to maintain plant cooldown rate P 1 within Technical. Specification limit Failure to corre.ct excessive flow. rate P 9

. of;the Emergency. Filtration System for

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th~e CR/TS,C subsequent to surveillance tes >

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- Failure to establish written procedure P 1 for securing HPI following safety feature actuati~o Failure'to establish written procedure P 1

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for loss, of power to the IC Failure to establish. written procedure P 1-

, for manually operated ATW system valv failureJto follow procedur.c to stop P 1 ATW pump Failure to establish written procedure P 1 for emergency manual operation of ATW control valv _

Failure to provide procedures for P 1 certain abnormal plant condition Failure to properly implement emergency P 1 procedure Lack of procedure for crimping too P 3

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-86-08 Failure to properly control calibrated V 3 I

tools and a volt. mete Failure to perform 10 CFR 50.59 evalua- IV 9 tion on SA-516 plate material.

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86-14' Failure to insure emergency plan P 6

. training is provided to all appropriate-personnel.

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' TABLE 2 (continued).

Rancho Seco Enforcement Items 06/01/85 - 06/31/86-

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(85-19 through 86-23)

Inspection Severity Functional Report No. 8

&ubject Level- Area 86-14- Failure to maintain emergency implementing .P 6

. procedures documen Failure to follow 10 CFR 50.54(q) require- P .6 ment Failure to comply with Technical Specifi- P 2 cations, Table 4.21-1, Footnote'(c).

Failure to establish a surveillance P 2 program pursuant to 10 CFR Part 50, Appendix I, Section IV . Failure to limit the. quarterly loss P 2 commitments to-a member of the general public pursuant to Technical Specifi-cations, Section 3.1. Failure to perform safety evaluations fo P 2 temporary . changes to radwaste processing systems pursuant to 10 CFR Part 50.5 Failure to develop and maintain procedures P 2-for controlling the transfer of . radio-

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activity . contaminated water pursuant to

" Technical Specifications, Section ;86-18' Failure to review modification by'PR IV 9 Fa'ilure to: hang abnormal tag per V- 9

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86-21 Failure to maintain continuous cleaning D

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,' , ' of nuclear service raw wate iFailure'to store quality record in the IV 9 g -vaul .

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!' * Severity Level P -;Pending final escalated enforcement actio '

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Table 3 SYNOPSIS OF LICEESEE EVENT REPORTS Functional- SALP Cause Code *

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B C D E X *

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Totals Plant Operations 3 1 0 5 0 1 10 Rad. Controls 1 0 0 0 0 0 1 Maintenance 2- 1 0 1 1 0 5

~ Surveillance 1 0 0 2 0 0 3 Fire Protection 1 0 0 1 0 0 2 Energency Preparedness 0 0 0 0 0 0 0 Safeguards 0 0 0 0 0 0 0

- Refueling 0 0 0 0 0 0 0- Quality Programs 1 5 0 0 0 0 6 and Administrative Controls Affecting Safety 1 Licensing 0 0 0 0 0 0 0 ,

1 Training H 1 0 0 0 _0 0 1 Effectiveness J

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Construction

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A - Personnel Error ( '

_B Design, Manufacturing or Installation Error C - External Cause l D - Defective Procedures

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E - Component Failure-X - Other

• - Cause not yet determined l'

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The:.above data are based upon LERs 85-06 through 86-1 Three of these LERs reported two separate events which were assigned to separate functional areas l

and cause codes.

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TABLE 4

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SUMMARY OF LERs (LER 85-06 through LER 86-10)'

Functional Cause LER N l Areas Code Subject

.85-0 B CRD Refurbished Breaker Failed to'Open on Undervoltage.During Bench Test 85-07' 4 D 4160 V.' Bus Undervoltage Relay'Out of Calibration 85-08 4 A Fire Barrier Surveillance Scheduling Error

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85-09 12 B Diesel Generator Control Circuitry Fails to Follow Normal Shutdown Sequence '

85-Id' 12 ~ A ' Reactor Coolant System Nonisolatable Leak at

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High Point' Vent; Missing Pipe Supports

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85-11 i D Reactor Trip From Unbypassed Shutdown High

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Pressure Trip Logic 85-12 El A Imp.roperly Latched Airlock. Door Compromises a Containment Integrity 85-13 'l B Diesel Generator Starts from Transient

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Overvoltage Condition 85-14 9 B Non-Class IE Breaker Installed in Class IE System 85-15 3,9 A D/G Started Inadvertently and Loose Connections Prevent Circuit Breaker Closure for Essential

' ~ HVAC Found 85-16 1 X Spurious Closure of DHR Suction Isolation Valve 85-17 9,12 B Seal Plate Omission Results in HEPA Filter Bank Leak f 85-18 1 D Diesel Generator Output Breaker Lockout 85-19 1 .D Excess Cooldown Rate After Reactor Trip Due to Open Feedwater Heater Relief Valves-85-20 12 B Essential HVAC Flow Controller Design Error Prevents Automatic Control After Return of Power

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TABLE 4 (continued)

SUMMARY OF LER '

(LER 85-06 through LER 86-10) _

Functio'nal Cause LER N sArean Code Subject

.85-21 3 Diesel-Generator Auto-Start Due to Lifted LeadL Error:by Maintenance Personnel 85-22- l' 'A Pressurizer. Liquid Sample Valve;Found Open in )

Violation of Tag-Out' Controls j l

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85-23 1 E Reactor Trip from Pressure Transient Induced by ICS Relay Resistance, Operator Error with Manual

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Feedwater Control with Stuck Recorder Pen f

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85-24 3 E Reactor Shutdown Due to Packing Glarid Leak' age

, of Pressurizer Liquid Sample Inboard Isolaticn -l l Valve

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85-25 ~1 A Reactor Trip and Overcooling from Loss of ICS 3 D Power Induced Transient'

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86-01 3,9- B EDG "A" and "B" Declared Inoperable During Cold -l

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86-02 12 B Erosion and Leaks in DHR Pump Casing Drain Line

86-03 2 A Containment Purge Unmonitored 1 86-04 ^ 5 A Missed Fire Watch

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B Seismic Spacing of Nuclear Service Batteries i

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86-06 '4 D Fire Protection System Overdue for Surveillance 86-0 B ~ Control Room Emergency HVAC High Flow Condition l 86108 5 D -Failure to Institute Fire Watch for Breached

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Penetration 1

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86-09' 1 A,D < Spurious ESFS Actuation a, ;

86-10' 12 . A,D = Redundant Cabling in Same Fire Area j i

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