IR 05000206/1986034
| ML13323B182 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 07/28/1986 |
| From: | Dangelo A, Huey F, Johnson P, Stewart J, Tang R, Tatum J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML13323B181 | List: |
| References | |
| 50-206-86-34, NUDOCS 8608120350 | |
| Download: ML13323B182 (34) | |
Text
1U.S. NUCLEAR REGULATORY COMMISSION
REGION V
Report N /86-34 Docket N '50-206 License N DPR-13 Licensee:
Southern California Edison Company P. 0. Box 800, 2244 Walnut Grbve Avenue Rosemead, California 92770 Facility Name: San Onofre Unit 1 Inspection at:
San Onofre, San Clemente, California Inspection conducted:
Ju e 28 through July 25, 1986 Inspectors:
- ff. ey, Senior Resident Date Signed Inspe or, U its 1, 2 and 3 J. war, Resident Inspector Date Signed A. D'A lo, Resident Inspector Date Signed-f1-J. tum, esident Inspector Date Signed
. C. a, Resident Inspector Date Signed Approved By:
P. H. Jo son, Chief Date Signed Reactor ojects Section 3 Inspection Summary'
Inspection on June 28 through July 25, 1986 (Report No. 50-206/86-34)
Areas Inspected: Routine resident inspection bf Unit 1 Operations Program including the following'areas:
operational safety verification, evaluation of plant trips and events, monthly surveillance activities, monthly maintenance activities, plant start up. from refueling and independent inspectio Insplction Procedures 25580,)13i707, 93702, 61726,, 62703, 71710, 71711, 72700, 61708 61710, 73052, 37701 42700, 920O', 92701, 92716:and 92702 were utilize '
OResults:
f the areas examined, no d viatiotis or violations were identifie PDR ADOCK 05000206
DETAILS 1. Persons Contacted Southern California Edison Company H. Ray, Vice President, Site Manager
- G. Morgan, Station Manager M. Wharton, Deputy Station Manager D. Schone, Quality Assurance Manager D. Stonecipher; Quality Control Manager R. Krieger, Operations Manager DShull, Maintenance Manager J. Reilly, Technical Manager P. Knapp, Health Physics-Manager B. Zintl, Compliance Manager D. Peacor, Emergency Preparedness Manager J. Reeder, Operations Superintendent, Unit 1 H. Merten, Maintenance Manager, Unit 1 R. Santosuosso, Instrument and Control Supervisor C. Couser, Compliance Engineer
.*Denotes those attending exit meetin The inspectors also contacted other licensee employees during the course of the inspection, including operations shift superintendents, control room supervisors, control room operators, QA and QC engineers compliance engineers, maintenance craftsmen, and health physics engineers and technician.
Operational Safety Verification The inspectors performed several plant tours and verified the operability of selected emergency systems, reviewed the Tag Out log and verified proper return-to service of affected component Particular attention was given tohousekeeping, examination for potential fire hazards, fluid leaks excessive vibration and verifiication that maintenance requests had beenoinitiatedfor equipment inneed of maintenanc The inspector noted~that housekeeping conditions on Unit 1 had shown an improvementsince the previous inspection perio The inspector identified minor steamand packing leaks inside containment during a pre-closeout inspe tion ofthe containment. The licensee implemented correctiveactions to stop the, sleak The inspectors'obsrveo return to servic activities described in the following procedures:' S1-V3.2, Plant:Startup from Hot Standby;. and SO1-V-r3_.2:,. Criticality following Refuelin No deviations orV.eiolations wete.note.
Evaluation of Plant Trips and Events Seismic Activity The San Onofre 'site 'experienced minor seismic activity on July 8 and
- July 13, 1986. The licensee implemented actions in accordance with approved stations procedures. No plant damage resulted.from these events. The unit was in Mode 3 during both event Reactor Trip on July 17, 1986 The unit tripped from about 3o power on July 17, 1986 as a result of a voltage transient on vital bus 4. The transient occurred when plant operators performed amanual transfer of vital bus 4 (VB 4)
from.its back up to its normal power supply. The voltage transient resulted from the break-before-make nature of the transfer switch design, which caused an approximately 130 msec. interruption in voltage. This allowed the P7 at-power permissive relay to drop out, resulting in a reactor trip (since the turbine was not latched).
The licensee has revised their procedures to correct this proble As part of the troubleshooting of the above problem, the licensee found several other problems. The following is a brief description of each of these problems:
(1) The B reactor trip breaker (RTB) was observed to spuriously trip free when electrically closed. The licensee performed extensive testing to confirm that the problem only occurs when trying to electrically close the breaker and has no effect on the trip capability of the RTB. The breaker manufacturer (Westinghouse) participated in the testing and agreed. The problem appears to involve minor friction and alignment related difficulties in the latch mechanism. These problems can only be corrected by major overhaul. The licensee Onsite Review Committee reviewed the breaker trouble shooting effort and agreed to plant start up subject to manually closing the RT The licensee is expediting overhaul of the old RTBs.and plans to replace the breaker at the next opportunit (2) During feed system operations the licensee observed that starting of the east feed pump can result in Vital Bus (VB) 4 voltage fluctuations similar to those caused by power transfe The licensee has determined the cause to involve some dynamic response problem when VB 4 is lined up to its new 4A inverte The licensee has not completed review of this problem, but it does not occur when VB 4 is lined up to its backup ac power sources. The licensee has aligned the plant with VB 4 powered from its. backup ac supply and plans to complete further evaluation and correction of the problem during the next scheduled outage. The installation of the 4A inverter was not
- a.cycle IX return to service-commitment. The licensee committed to the 4A inverter for cycle X (startup following 1987 refueling outage).'
'3 (3) During VB 4 troubleshooting efforts SCE discovered a wiring problem in feedwater regulating yalves FCV-458 and CV-14 These wiring problems did not appear to affect valve function nor did they appear to contribute to the V 4 problem Although the valve was wired in accordance with'the applicable schematic drawing, the drawing was in error. The licensee has corrected this proble (4) During VB 4,' troubleshooting the licensee also noted. anomalous behavior-of the reactor plant annunciators.. For example, depressing the reactor trip button caused unexpected variations in the intermediate range nuclear instruments and radiation monitoring instruments. Theilicensee determined the problem to involve a deficient' annunciator relay and corrected the proble.
Monthly Surveillance Activities The inspectors observed the following surveillance tests during unit return to. service following the eighth refueling outage:
SO1-12.3-26 Auxiliary:Feedwdter Pump Operability Test S01-12.3-10 Die sel Gener ator Load Test Theinspector observed several 'unsuccessful tests' of the steam driven auxiliary feedwater pump overspeed trip.function. The licensee adjusted the throttle valve1_.ovJrspeed mechanism and performed 6 successful overspeed trip test.
Monthly Maintenance Activities
'Inspectors observed the following maintenance activities during the period:
Replacement ofbearing housing bolt insulation washers on the west feedwater pump moto Post maintenance and inservice testing of the auxiliary feedwate main steam-pressure regulating control valve.(CV-113).
Hydrostatic test of auxiliary feedwater pump turbine steam inlet relief valve (CV-3206) pipin Post maintenance testing of auxiliary feedwater steam piping weld Main turbine vibration testing following turbine overhau The inspectors observed that Quality Control inspectors were present and actively involved in the above maintenance activities. -These maintenance activities were observed to have been completed in accordance with
.applicable procedures and all test instruments were noted to be properly calibrate No deviations or violations were note.
Engineered Safety Feature Walkdown'
The inspector performed a walkdown of the auxiliary feedwater system and verified that all the valves described in procedure S01-12.3-36, Auxiliary.Feedwater System Safety Related Alignment, were in their proper position No deviations or violations were identifie.
Plant Start Up from Refueling The inspector observed portions of the following low power physics tests:
S01-V-Criticality Following Refueling S01-V-Boron Endpoint Determination S01-V-Isothermal Temperature Coefficient Measurement at Hot Zero Power SO1-V-Rod Worth Measurement S01-V-Reactivity Computer Installation and Alignment S01-V-3.10 Base Power Level Determination The inspector observed initial criticality following the refueling outage on July 15, 1986. The inspector observed that inverse count rate and source multiplication predictions were made by operating personnel during the,startup. Criticality was achieved consistent with these predictions at 130 steps on Control Group 2. This was 70 steps (a reactivity difference of 0.54%) below the estimated critical position (ECP)
predicted using data supplied by Westinghouse. This difference was within the difference of.1.0% reactivity allowed by Section 4.8 of the Technical Specifications. The inspector noted that,.following adjustments to ECP data by the licensee, the subsequent criticality on July 22, 1986 occurred within 0.02% reactivity (3 steps) of the EC No deviations or violations were note.
Independent Inspection IE notice 86-52 describes wiring insulation deterioration problems which have-been observed on Foxboro controller wiring harnesses. Resident and Vendor Program Branch inspectors reviewed this notice with the licensee and noted that.Foxboro wiring harnesses currently in the licensee's stock system showed insulation deterioration.problems similar to those described in the IE notic The licensee has determined the location of these harnesses on installed plant instruments and has completed preliminary inspections of those instruments which have a reactor protection system function. This preliminary inspectionidentified no wiring insulation deficiencies and on this basis, the licensee determined that continued plant operation is warranted pending replacement of all involved wiring harnesses during'the next scheduled plant outag The inspector review'ed the lidensee's inspectionresults and basis for continued plant operation and noted that additional inspection effort appears warranted in order to provide adequate assurance that installed plant instruments do not include deteriorated wiring. The licensee agreed to evaluate the need for a more detailed and broader scoped inspection effor This is an open item (50-206/86-34-01). NRC Action Plan Following the loss of power and water hammer event which occurred-on November 21, 1985, the NRC developed an Action Plan.for the review of licensee actions required as a result of the event and the subsequent Incident Investigation Team (IIT) report. This plan involved actions by Region V, NRR, and I Included as Attachment 1 to this inspection report is a listing of these NRC actions taken as a result of the event, including references to the closing documentation for each issu In addition to those related to the November 21, 1985 event, the licensee also completed a number of significant efforts during.the recent refueling outage to comply with previously established NRC requirements or commitments. NRC review actions related to these licensee activities are tabulated in Attachment 2 to this repor..
Exit Meeting On July 28, 1986, an exit meeting was conducted with the licensee representatives identified in Paragraph 1. The inspectors summarized the inspection scope and findings as described in this repor SII
ATTACHME
@ (IIT Items)
Required Status/
for Res Due Date Completion Item Description Startup Source Office (SCE Item No.)
Date 1...
Implement and coordinate the staff Stello memo IE/VPB 6/6/86 SONGS 1 Plant specific and industry actions necessary 2/4/86 actions complete to assure the reliability of Enclosure generic actions ongoing safety-related check valve Item 1 Areas to be evaluated include: Adequacy of licensee's report Yes Stello memo IE/VPB 6/6/86 Evaluation of licensee on root cause analysis and 2/4/86 (lead)
submittals of 3/22/86, proposed corrective action Enclosure and 4/8/86, 5/1/86 and Item 1 NRR/PWR-A 5/5/86 complete
..
Review documented in J. Taylor to J. Martin memo dated.6/6/86.'
-Note: The hydrodynamic aspects of the design differences between the failed and replacement check valves will be reviewed by IE and factored into the overall feedwater system design review in item 3.b. The overall feedwater system design review is listed separatedly to highlight the importance of this review and to allow listing all NRR design change reviews in one locatio Adequacy of check valve design Yes IIT IE/VPB 6/6/86 Complete. Documented for SONGS 1 application 3.3(Pg.3-6)
(lead)
(34, 67)
in J. Taylor to at time of November 21 Stello memo RV J. Martin memo dated even /4/86 NRR/DSRO 6/6/8 Encl.Item 1
& PWR-A
ATTACHME (IIT Items)
Required Status/
for Res Due Date Completion Item Description Startup Source Office (SCE Item No.)
Date Note:
A review of the design changes to the feedwater system is covered in item The results of this evaluation will be considered as appropriat )
Determine which valves RV IE&RV/SONGS 6/6/86 Complete 6/6/86 are only partially open Residents**
during nominal operating condition )
Review existing inspection RV IE&RV/SONGS 6/6/86 Complete 6/6/86 or test result Residents**
3)
Review existing
.
.RV IE&RV/
6/6/86 Complete 6/6/86 maintenance historie SONGS Residents**
4)
Observe disassembly and RV IE&RV/
6/6/86 Complete 6/6/86 perform visual inspection SONGS of selected check valves Residents**
based on the results of the 'above review *The SONGS-1 plant specific issues will be completed and a plan to address the generic aspects will be developed by this dat **Resident findings documented in report 86-1 ATTACHME (IT Items)
Required Status/
for Res Due Date Completion Item Description Startup Source Office (SCE Item No.)
Date 1.c Generic.evaluation of adequacy No IE/NRR IE/VPB 6/6/86*
In progress of check valve designs for this and applicatio (other systems Chilk's are addressed separately)
memo 2-/7/86 1)
Perform vendor inspection JE IE a)
Anchor Darling 1pe/86t Cmpled on schedule (99900053/86-01 -2/25/86)
b)
Atwood Morrill 2/10/86 Completed oschehdu-le 99900049/86-01 6/4/86)
c)
MCC Pacifi 2/10/86 Comple ted on schedulet S(999005A6 0-1 3/31/86)
d)
Crane 3/3/86'
Completed on schedure-(9990f048/86-01 5/27/86)
e)
Velan
Completed on schedule (99900 6/86-01 6/13/86)
2)
Review failure data and failure IE IE 6/30/86 Completed Memo mode E.Yachiniakt
.E. Merschoff;7/14/86 a)
LERs, 50.55(e), PT21, PNO b)
NPRDS c)
Vendor Supplied'
d)
Licensee Supplied 3)
Review check valve JE IE 4/22186 Complete T. Taylor to experience at site J. Martin memo 6/6/86
- Hope Creek 2/06/86 Completed on schedule
- Millstone 2/10-14/86 Completed on schedule
-
North Anna 2/10-14/86 Completed on schedule
- Limmerick 3/24-25/86 Completed on schedule
- Peach Bottom 3/25-26/86 Completed on schedule
ATTACHME
- (IIT Items)
Required Status/
for Res Due Date Completion Item Description Startup Source Office (SCE Item No.)
Date 4)
Review comments and IE IE 6/6/86 Meeting held 4/7/86 &
intended actions of 5/21/86 (w/Owners Owners' Groups meeting Group).
Documented Zech to Grimes 4/22/86 and 6/30/86 comments Volmer toTucker 6/13/86 5)
Determine adequacy of check IE IE 6/6/86§ SONGS1 Plant specifi valve design for this actions complet application using input Generic-actions from C.1 to C.4 abov continuin.,d. Adequacy of'Inservice Testing IIT IE/VPB (lead)
6/6/86 SONGS1 Plant specific (IST) Program and procedures to (pg.6-14)
NRR/DSRO actions complet detect degraded and failed and Stello PWR-A/EB Taylor to Martin Memo valve memo 2/4/86
.6/6/86.. Generic Encl. Item 1 actions continuin )
a. NRR review of SONGS 1 TBD NRR NRR/DSRO 3/25/86 Draft evaluation IST program docketed and PWR-A (17; 54,
-completed 3/1/86 prior to the even, 72)
b. NRR review of SCE's TBD NRR PWR-A/EB 6/11/86 Ongoing. Restart 3/3/86 revision of IST issues addressed in progra /6/86 IE memo (by concurrence) Licensee submittal revised 7/3/86 Technical Specification change due in August 198 )
Evaluate Adequacy of IST No IE IE 6/6/86 Memo to Commissioners Programs (Generic)
in preparation 7/28/86
- The SONGS-1 plant specific issues will be completed and a plan to address the generic aspects will be developed by this dat ATTACHME
@ (TIT Items)
Required Status/
for Res Due Date Completion Item Description Startup Source Office (SCE Item No.)
Date a)
Visit Plants
-
Millstone 2/10-14/86 Completed on schedule North Anna
.2/10-14/86 Completed on schedule b)
Review a sample of-16 IE 6/6/86 Complete Yachimiak to IST programs Merschoff memo 7/14/86 c)
Review comments from-IE 6/6/86 Meeting w/owners Owners'
Group group held 4/7/86 and 5/21/86. Closed Zech to Grimes Mtg summaries dtd 4/22/86 and 6/30/86 d)
Based on a), b) and c)
IE/VPB and 6/6/86*
Memo to Commissioners above, make recommendations NRR/DSRO in preparation 7/28/86 on portions of Generic issue II.E.6.1 which should b accelerated or any more immediate licensee actions that should be considere )
Evaluate adequacy of Yes IE IE/RV
-
6/6/86 Complete IR 86-15 existing implementation (17, 53, issued 6/6/86 of IST program for.SONGS )
(Including check valves and other valves).
(Including the following considerations: test frequency; acceptance-criteria; need for periodic disassembly/
inspection & QA involvement)
'The SONGS-1 plant specific issues will be completed and a plan to address the generic aspects will be developed by this dat ATTACHME (IIT Items)
Required Status/
for Res Due Date Completion Item Description Startup Source Office (SCE Item No.)
Date 4)
Review of SONGS 1 IST Yes NRR IE/VPB 6/6/86 Complete 6/5/86 IE program requirements in NRR/PWR-A/EB (17, 54, to Martin Letter light of November 21, 58, 72)
1985 even.e. Evaluation of check valves (and Stello memo IE/VPB (lead)
6/6/86 Complete Taylor to related testing programs). for 2/4/86 NRR/PWR-A (67)
Martin memo 6/6/86 other safety-related systems, Encl.Item 1 RV such as RHR syste )
Evaluate SONGS 1 check Yes RV IE&RV/SONGS 6/6/86 Complete. Report valves in non feedwater Residents 86-15 and 86-16 system application as per sub-items listed in l )
Generic adequacy of chec No IE/NRR IE/VPB (lead)
6/6/86*
Memo to Commissi6ners valves (and related testing NRR/DSRO in preparation 7/28/86 programs) in other safety related systems as per sub items listed under item lb including review of check valve dat.f Evaluate check valve maintenance Yes IIT IE&RV/SONGS 6/6/86 IE Inspection conducted program implementation for SONGS-1:
(pg. 6-12)
Residents (53, 67)
3/86. Report.86-15 issued 6/6/86 1)
Review adequacy of valve RV Resident findings preventive maintenance (PM)
reported in inspection progra report 86-2 )
Evaluate the adequacy RV Resident findings of licensee trending of reported in inspection IST and maintenance result report 86-2 *The SONGS-1 plant specific issues will be completed and a plan to address the generic aspects will be developed by this dat ATTACHME
@ (IIT Items)
Required Status/
for Res Due Date Completion Item Description Startup Source Office (SCE Item No.)
Date 3)
Evaluate the adequacy RV Resident findings of QA involvement in PM reported in inspection progra report 86-2 Evaluate check valve maintenance No RV IE/NRR-6/6/86*
Meeting held with programs genericall owner's group.4/7/86 And 5/21/8 Documented in G. Zech to B. Grimes memos dated 4/22/86 and 6/30/8.
Assess the need to reevaluate USI A-1 No IIT NRR/DSRO 6/30/86 Completed. Documented to specifically address the potential (pg. 6-7,8&9)
(29, 57)
in memo, Denton to for and prevention of condensation and Stello 7/7/8 induced water hammers in feedwater Stello memo piping (assume the issue concerning 2/4/86 check valve integrity will be resolved Encl.Item 2 in item 1).
and Chilk's memo 2/7/86
Adequacy of SONGS-1 Design Features Yes Stello mem NRR/PWR -A 6/6/86 Complete:
See Below (other than specific check valve 2/4/86 design)
Encl.Item 3 Implement and coordinate Stello memo NRR/PWRA 6/6/86 the staff's actions to 2/4/86 reevaluate the following Encl.Item 3 San Onofre design features:
1)
Lack of automatic loading of IIT q4.14 PWR-A/
5/16/86 Complete. Licensee's the diesel generatorsfollowing (Pg. 4-16)
EICSB (15)
submittal 3/2/86 and a loss of power even and 4/8/86. Completed Chilk's memo 5/16/86. Documented 2/7/86 in restart evaluation 6/5/8 ATTACHME (IIT Items).
Required Status/
for Res Due Date Completion Item Description Startup Source Office (SCE Item No.)
Date 2)
Lack of remote control of IIT PWR-A/
5/9/86 Completed.5/13/8 steam.line isolation valves and (pg. 3-9)
PSB an (16, 86)
Documented in restart resultant impact on assurance and RSB evaluation 6/5/8 of steam generator availability (pg. 4-1)
to remove decay heat (in even & Commission of steamline.or feedline break).
Brief 3/18/86 3)
Lack of steam generator IT PWR-A/
5/9/86 Completed 5/13/8 blowdown status in control (pg. 3-10&11),
PSB (7, 26, Documented in restart room or auto termination 7.2., 74)
evaluation 6/5/8 capability (pg. 7-9)', and 8.7 (pg. 8-3)
4)
Adequacy of the licensee's Stello memo PWR-A/
.5/16/86 Completed 5/15/86, design change to eliminate 2/4/86 EICSB (4, 5, documented in restart spurious SI indication on Encl.Item 3 75)
evaluation 6/5/8 loss of power.(SI-annunciator and SIS sequencer surveillance panel)
5)
Non-safety related auto IIT 5 PWR-A/
5/16/86 Completed 5/15/86, sequencer (reliability and (pg. 3-6),
EICSB (2,81)
documented -in restart impact on station blackout).
7.2. evaluation 6/5/86.
(pg. 7-5), &
4.12. (pg. 4-11)
6)
Impact of interlock between IIT 4.1 PWR-A/
5/16/86 Completed 5/15/86, reactor bypass breaker and (pg. 4-13)
EICSB (13)
documented in restart diesel generator output breaker evaluation 6/5/8 on electrical power reliabilit )
Adequacy of labeling for selected IIT 4.16. PWR-A/
- 5/9/86 Completed 5/9/86, control room indicator (pg. 4-20)
EICSB (19, 31)
documented in restart 7.2. !evaluation 6/5/8 (pg. 7-4)
ATTACHME*
(IIT Items)
Required Status/
for Res Due Date Completion Item Description Startup Source Office (SCE Item No.)
Date 8)
Reliability of power to IIT PWR-A/
5/16/86 Completed 5/15/86, vital buses, e.g., power (pg. 3-6),
EICSB (10, 79, documented in restart to important control 4.12.1 (pg.4-9),
80)
evaluation 6/5/8 room indications and 4.12.4 (pg.4-13),
control.12.5 (pg.4-14),
4.17 (pg.4-21 thru 24)
9)
Increased reliability of IIT 5 PWR-A/
5/9/86 Completed 5/13/86, 4KV power supplies (pg. 3-2),
EICSB (1, 3)
documented in restart (Includes evaluation of 54.1 evaluation 6/5/8 cause of failure of C (pg. 4-11),
transformer power cable).
4.13 (pg.4-15),
4.14 (pg.4-16),
17.2.1.5 (pg.7-6),
8.1 (pg.8-1)
a)
Cable reliabilit (77)
b)
Alternate immediate (84)
source of offsite power (e.g., additional reserve transformer).
3.b Evaluate adequacy of SONGS-1 IIT 6. NRR 6/6/86 Licensee's submittal feedwater system design (pg. 6-9)
PWR-A/PSB (29, 30)
of 4/8/86.reviewe Documented in restart evaluation 6/5/8 )
Water hammer design NIRI PWR-A/EB Design considerations considerations/engineering to withstand water hammer are not require Documented in restart evaluation 6/5/8 ATTACHME (lIT Items)
Required Status/
for Res Due Date Completion Item Description Startup Source Office (SCE Item No.)
Date 2)
Water hammer. design NRR PWR-A/PSB Completed 5/13/86, considerations/systems documented in restart aspects. Includes review evaluation 6/5/8 of licensees test program to assure that water hammers do not occur in feedring or other parts of syste )
Possible instrumentation NRR PWR/EICSB (57)
Further NRR review to indicate impending not required. Concept water hammer condition impractical per licensee. Restart Evaluation completed 6/5/8 )
Adequacy of feedwater NRR PWR-A/EB (33, 69-73 Completed 5/14/86, repair/system integrity 82)
documented in restart and material consideration report 6/5/8 Review and inspect-selected Yes RV RV/SONGS 6/11/86 Complete. Inspection design change Residents of modifications documented in reports 206/86-22, 86-29 and 86-3 )
Steam generator blowdown IIT (26, 27, Modification status indication or (Pgs. 3-10&11)
74)
inspected automatic terminatio.2. (Pgs. 7-9), and 58.7 (Pg. 8-3)
2)
Modifications to eliminate licensee I-T 17.2. (4, 5, Modification inspected spurious SI indication commitment (Pg. 7-4)
75)
3)
Improved labeling for IIT 54.16. (19, 31)
No modification selected control room (Pg. 4-20) and planned for RTS indicator.2. (Pg. 7-4)
ATTACHME (IIT Items)
Required Status/
for Res Due Date Completion Item Description Startup Source Office (SCE Item No.)
Date 4)
Continuity of power to IIT. 4.1 (10, 79, Modification inspected event computer and (Pgs. 4-21 thru 24)
80)
vital buse.4 (Pg. 3-6),
I4.12.5 (Pg. 4-14),
14.12.1 (Pg. 4-9),
4.12.4 (Pg. 4-13)
5)
Increased reliability of IIT 58.1 (Pg. 8-1),
(1, 3)
4KV power supplie.12.3 (Pg. 4-11),
113.2 (Pg. 3-2),
14.13 -(Pg. 4-15),
4.14 (Pg. 4-16),
57.2.1'.5 (P ) Auto loading of (15)
-
No modification diesel generator planned Loss of voltage (87)
Modification-inspected automatic sequence (LOVATS modifications) Reactor bypass/diesel licensee (13)
Modification inspected generator output-commitment breaker interloc Environmental licensee (77)
Modifications inspected protection for 4KV commitment cable Alternate 4KV power (84)
No modification sourc planned for RTS 6)
UPS and automatic reset IIT (85)
Modifications inspected for TSC compute.2.2.4 (pg. 7-10)
7)
Feed line void detector RV (57)
No modif. planned
ATTACHME
@ (IIT Items)
Required Status/
for Res Due Date Completion Item Description Startup Source Office (SCE Item No.)
Date 8)
Modifications and repairs
]RV (33, 69-71,.
Modif. & repairs to feedwater system 73, 82)
inspected. NRC NDE including independent exam. completed 4/1 ND (86-13) Abnormal Condition and Post-trip Review Concern Evaluate generic NRC requirements No IIT 7.2. NRR 6/6/86 Completed 5/28/8 for ensuring that sufficient (Pg. 7-10) &
EICSB/PWR-A Memorandum to EDO in event data are retrievable to Stello memo preparation 7/23/8 accurately reconstruct event 2/4/86 following a loss of offsite powe Encl.Item 4 Evaluate the licensee's process Yes IIT RV/SONGS 6/6/86 Licensee's submittal for abnormal condition and 57.2. Residents (63)
received 4/8/86'
post-trip review, including (Pg. 7-1O)
Inspection completed
,involvement of:.
5/9/86. Report 206/86-2 )
Onsite Review Committee IIT (61)
(e.g., noise evaluations (pg. 6-12)
in feed line B prior to
& Commission event).
Include addition brief 3/1.8/86 of "expert" to OSR )
Offsite Review Committe IIT (pgs. 6-12&13)
3)
Quality Assuranc RV Evaluate adequacy and Yes IIT 7.2. NRR/PWR-A/
6/6/86 Completed 5/9/86, reliability of post-trip (pg. 7-10) &
EICSB (11)
documented in restart data retrieval equipmen Stello memo evaluation 6/5/8 /4/86 Encl.Item 4
ATTACHME
@(IT Items)
Required Status/
for Res Due Date Completion Item Description Startup Source Office (SCE Item No.)
Date 1)
Critical Function IIT (11)
Monitor not reset 7.2. after troubleshootin (Pg. 7-10)
2)
Continuity of'power IIT 14.;1 (85).
to event compute (pg.- 4-23) Evaluate the overall adequacy of Yes IIT 5 RV/SONGS 6/6/86
'Licensee's submittal SONGS 1 maintenance record (pg. 6-12) &
Residents (53)
received 4/8/86 Stello memo Inspection reported 2/4/86,
in 206/86-22 Encl.Item 5 Completeness and Retrievability RV of records:
Include evaluation-of cancelled work orders on check valves per' IIT Report QA overvie. RV Trending RV Adequacy of Procedures Verify licensee actions to Yes RV/SONGS 6/11/86 Licensee's submittal correct the. following Residents received 4/8/8 identified deficiencies Inspection reported with site procedure in 206/86-2 )
Lack.of adequate precaution's IIT 57.2. (41)
on length of time. 'diesel:
(pg. 7-6)
generators can operate unloaded without. AC power"-to.radiator fans was improperly deleted from procedur ATTACHME
@(IIT Items)
Required Status/
for Res Due Date Completion Item Description Startup Source Office (SCE Item No.)
Date 2)
Lack of provisions for IIT (57, 64)
recognizing and preventing (pg. 6-2,3&4)
conditions which allow the initiation of water hammer )
Inadequate instructions for IIT (40)
manually bringing power onto (pg. 3-6),
dead buses and for responding 7.2. to malfunction of the loss (pg. 7-5),
of ac power automatic 4.12. sequence (pg. 4-11)
4)
Inadequate instructions for IIT 8.1 (pg.8-1),
(37, 55)
trouble shooting of 4KV 4.12.3 (pg.4-11),
bus ground.2 (pg.3-2),
54.13(pg.4-15),,
4.14 (pg.4-16),
7.2. (pg. 7-6)
5)
Lack of provisions for IIT 7.2. (39)
identifying alternate (pg. 7-4).
methods of verifying SI actuatio )
Need for revision to AFW IIT (24, 42, system flow control procedures (pg. 6-3)
44)
to factor in effect of flow on reactor coolant system temperatur )
Procedure for going onto UT (9)
RHR cooling implied clearing (pg. 8-3),
of isolation valve interlock 3.8 (pg. 3-12&13),
at 400 vice 370 psig (Also 4.10 (pg.4-8),
training guide #22).
7.2.1.8 (pg.7-8)
ATTACHME
- (IIT Items)
Required Status/
for Res Due Date Completion Item Description Startup Source Office (SCE Item No.)
Date 8)
Need for administrative (15)
time limit on loading diesel generators following loss of station powe Assess appropriateness Of Yes IIT NRR/
6/6/86 Completed 4/17/8 paralleling buses with (pg. 3-2),
PWR-A/
(18)
Documented in restart indicated ground faul.1 (pg. 5-1)
EICSB evaluation 6/5/8.2. (pg. 7-1) Evaluate overall program Yes Stello memo RV/SONGS 6/6/86 Inspection completed-for developments of procedures 2/4/86 Residents (36)
5/9. Report 206/86-2 in light of the above Encl.Item 6 inadequacie.
Adequacy of trainin Yes Stello memo RV/SONGS 6/11/86 Licensee's submittal 2/4/86 Residents (45)
'of 4/8/86 reviewe Encl..Item 6 Completed 86-28 6/3/8 Verify the adequacy of Yes Reactor 6/11/86 Licensee's submittal operator training in the Safety of 4/8/86 reviewed following areas:
Branch Inspection in report 86-2 )
Troubleshooting and IIT 57.2. (49)
isolating grounds (pg. 7-1 thru 4)
including bus and transformer ground )
Transfer of loads between IIT 7.2. (51)
"
4KV buse (pg. 7-1)
3)
Operator response to IIT 57.2. (46, 48, loss of offsite electrical (pg. 7-4)
52)
powe ATTACHME
@ (IIT Items)
Required Status/
for Res Due Date Completion Item Description Startup Source Office (SCE Item No..)
Date 4)
Resetting Unit Trip IIT 7.2. (3, 52)
to allow reenergization (pg. 7-5)
of onsite electrical buse )
Controlling SG Blowdown IIT.(47)
"
"
(pg. 3-10&11)
6)
SLSS sequencer panel IIT 4.13 (50)
"
indications (p &16)
7)
Not.notifying NRC that IIT 7.2. (38, 60)
a UE had been declare (pg. 7-9), &
7.3.2 (pg. 7-15) Evaluate implementation of Yes IIT.
RV and 6/11/86 Licensee's submittal technical specification action (Pg. 3-2)
PWR-A/FOB (56)
pf 4/8/86 Report statements when warranted, e.g.,
206/86-22. NRR input reluctance to fully isolate documented.in restart failed tranformer and removal evaluation. 6/5/8 from service of one feedwater pum Assess operators training and Yes Commission Reactor 6/11/86 Inspection Report 86-28 knowledge in the use of prints brief Safety and drawing /18/86 Branch d.-
Assess appropriateness of Yes Commission Reactor 6/11/86 Inspection Report 86-28 mix of training for normal brief Safety operation thru major accidents 3/18/86 Branch Emergency Notification Stello memo IE/DEPER (lead) 6/6/86 Complete, Report 86-1 /4/86 RV Encl.Item 7
ATTACHME
- (IIT Items)
Required Status/
for Res Due Date Completion Item Description Startup Source Office (SCE Item No.)
Date Verify the adequacy of the Yes IIT 197.2. RV/
5/14/86 Complete Report licensee's procedures and (pg. 7-9) &
Emergency (38, 60)
206/86-1 training for reporting of Stello memo Preparedness events to NRC Operations 2/4/86 Section (lead)
Cente (See item 7. Encl.Item 7 IE/DEPER above) Evaluate NRC policy for No IIT 7. IE/DEPER 6/6/86 Complete. Documented allowable uses of the EN (pg. 7-11&14)
in memo's Perkins to Zech dated 2/10/86 1)
Use of NRC personnel as IIT 97.3. and 2/13/84.
Final ENS communicators (pg. 7-14)
documentation, memo Grimes to Kirsch 6/11/8 )
Actions to improve NRC IIT 7. determination of overall (pg. 7-11 thru 14),
plant status during 7.3.2 (pg. 7-15)
event )
Site specific training IIT 57.3. of headquarters duty (pg. 7-12)
officer )
Licensee responsibility IIT 7.3. (38)
to provide communicator (pg. 7-14)
when requeste )
Qualifications of licensee IIT 7.3. (38)
communicato (pg. 7-12),
57.3. (pg. 7-14) Evaluate spurious ringing of Yes IIT 8.10 RV/EP 5/14/86 Complete Report ENS phones during even (pg. 8-4)
Section (lead)
(12)
206/86-1 IE/DEPER
ATTACHME (IIT Items)
Required Status, for Res Due Date Completion Item Description Startup Source Office (SCE Item No.)
Date Evaluate the adequacy of licensee Yes IIT 7.2. IE/DEPER 5/14/86 Complete Report 86-1 procedures and training for (pg. 7-8)
(60)
notifying on-shift personnel RV/EP Section of an emergency even (lead) Evaluate whether a backlog'of Yes lIT NRR/
5/186 Cueem 4/28/86 license amendments 'and technical (pg. 6-10) &
PAD-1 (lead),
enton to "Stello specification changes contributed-Stello memo PWR-A and to delays in approving the licensee s 2/4/86 DSRO IST progra Encl. Item 8 10. -Evaluate effect of long Yes Chilk's RV (lead)
3/10/6 Li'cen s submittal outage period on plant component /7/86 55 IE (62)
".
3/2/8 (clo'sely tied to item 11, below)
Commissioner NRR
'
Completed Stello t Bernthal to Commissioners 4/.
Perform a comprehensive evaluation Yes RV-
'RV/SONGS 6711/86 Complete Report 86-2 of licensee. actions to implement Residents 66)
an integrated program for -review and upgrading of overall plant. material
conditibn prior to restart of SONGS'. Review existing maintenance RV and test'data:for key safety related systems and "systems that are. important to on-line
'plant reliabilit Review the overall backlog R of maintenance orders not completed prior to restar Review the licensee program RV
.for operational readiness testing of' key safety-related systems and, systems that are important to on-line plant reliabilit ATTACHME
@(IIT Items)
Required Status/
for Res Due Date Completion Item Description Startup Source Office (SCE Item No.)
Date Perform a comprehensive RV walkdown of key safety related systems -and systems that are important to on-line plant reliabilit Review licensee-implementa-RV tion of Area Management Program (AMP). Perform independent measure-RV Inspection completed ments to confirm plant-411/86 Repbrt 86-13 material condition (NDE Van).
issued...
Include measurements of steam and feedwater system wall thickness to detect erosion of pipe wal.
Evaluate the licensees effort Yes NRR PWR-A/EB 6/6/86 Completed 5/12/86 to assure that the 'steam generators Documented in restart low-levels did not damage or evaluation 6/5/8 leave damaging chemical materials in the steam generator.
Assess failures on automated Yes IIT 8.11 RV 3/11/86 Closed Inspection security syste (pg. 8-4)
Report 50-206/86-03 1 Propose improvements to Technical No RV RV 7/30/86 RV input to NRR Specifications based on revie NRR completed 3/7/8.
Assess licensee's program and No Commission RV/SONGS 5/30/86 Complete Report 86-22 efforts to learn lessons from Brief Residents other plants (conventional)
3/18/86 within their systems, and other nuclear plants (e.g.,
Conn Yankee and Japanese plants)
ATTACHME W(IIT Items)
Required Status/
for Res Due Date Completion Item Description Startup Source Office (SCE Item No.)
Date 1 Assess licensee actions regarding Yes NRR NRR 6/11/86 Complete. Documented loose parts in the steam generator in 6/5/86 Restart feed rin Evaluatio ATTACHMENT on IIT Items)
SCE Action Responsible Due Status/
Item Description Source List N Office Date Completion Date Region V Inspection Activities RV Inspect the new dedicated RV-SONGS 6/11/86 Licensee modification safe shutdown facilit Residents and associated inspection complete. Includes LLNL contract effor Issued in report 86-2 Concrete placemen Installation of App. R diesel generato Installation of control and power cabl Installation of third Auxiliary Feedwater (AFW)
pump and associated pipin.
Inspect Environmental RV-SONGS 6/11/86 Licensee modification Qualification upgrading, Residents and associated inspection complet Includes LLNL contract effor Documented in 86-2 Replacement of 45 electrical containment penetration Review post maintenance operational testing of selected equipment affected by penetration wor Replacement of two long term recirculation pumps in containmen ATTACHMENT on IIT Items)
SCE Action Responsible Due Status/
Item Description Source List N Office Date Completion Date Replacement of original electric AFW pump moto Replacement of instrument and control cable inside containment for RHR and SI MOV' Replacement of valve operator.
Inspect seismic upgrading RV-SONGS-6/11/86, Licensee modification of piping, pipe supports, Residents and associated inspection and cable tray complete. Includes LLNL contract effor Documented in report 86-2 Installation of new salt water pipin Installation of new recirculation pipin Upgrade of accident mitigating system piping from 0.5g to O.67g by installation of approx.. 300 pipe support Installation of new AFW piping for 3rd AFW pum Upgrade of cable tray supports to 0.67g and code allowable ATTACHMENT on IIT Items)
SCE Action Responsible Due Status/
Item Description Source List N Office Date Completion Date Review open items list for RV-Staff 6/11/86 Completed 3/28/86 items to be completed prior Residents to restart. Include items which may reflect on material condition or involve management systems which contributed directly to.the 11/21 even Complete inspection and assessment of the adequacy of licensee actions for: IEB's Inspection complete-85-Auxiliary Feed Pumps Huey
'."documented in 6-22 85-03 -
MOV Failures Clark I
Inspected 206/86-ih, 86-26 licensee action incomplete. Action to date meets NRC Schedule IE concurs.,,
b..Enforcement Items 84-28-01 -
Conduit Seal Ivey Closed'Report 86-2 Missing 85-20-01 -
Failure to Huey Inspection complete follow. Verifi-Report 86-2 cation of Valve Position Procedur Failure to
.Clark Completed 5/16/86 implement IST
.
Report 206/86-11 requirement Procedure Huey Inspection complete Violations Report 86-2 regarding Steam Driven AFW pum ATTACHMENT on IIT Items)
SCE Action Responsible Due Status/
Item Descriptio Source List N Office Date Completion Date 85-33-03 -
Improper mod Huey Inspection complete to AFW pump Report 86-2 oil sight glas As found settings Ivey Inspection complete of-MS safety Report 86-2 valve Followup items Review followup items Narbut
.
Complete list for important, Huey currently relevant items important. to North safety for restart Information Notices 84-37 -
Use of lifted Melfi Closed 206/86-11 lead Solenoid Valve Melfi Closed 206/86--11 hold down nu Relay calibratio Melfi Closed 206/86-11 85-66 -.As-built Melfi Closed 206/86-11 discrepancie g ATTACHMENT*on IIT Items)
SCE Action Responsible Due Status/
Item Description Source List N Office Date Completion Date 85-71 -
CILRT D'Angelo Inspection complete, Report 86-2 Battery.Problem Phelan Inspection Complete Report 86-2 Load Sequencers Ivey Inspection complete
- for Report 86-26 86-06 -
EQ of Limitorque D'Angelo Inspection complete Wiring Report 86-22 Temporary Instructions TI-15-46 -
ATWS Procedures Ivey Complete superceded by GL-83-28 TI-15-69 -- TI for IEB-85-01 Huey Inspection complete (AFW Pump)
Report 86-22 Unresolved-Ite ns 85-12-01 7CRT leakage D'Angelo Inspection complete indeterminate Report 86-22 85-26-04 -
IST Records Clark Closed 5/16/86 Report 206/86-11 85-37-02 -
No calibration Ivey Inspection complete data for MS safeties Report 86-26
.
Part 21 Reports 84-00-P -
BBC (ITE-60) Relays Ivey Closed Report 86-26 85-17-P -
Electric heat trace Ivey Complete 86-26 plus all TDI DG Part 21' Phelan Complete. Report 86-20 TMI Items Ivey Inspection complete 86-2 ATTACHMEN on IIT Items)
SCE Action Responsible Due Status/
Item Description Source List No Office Date Completion Date Inspection of control RV/NRR Inspection completed room ventilation system Willett Report s 86-25, 86-31 for compliance to requir-SE issued 7/11/86 Rossi ments and commitment to Dudley Inspection of selected Qualls Inspection complete Appendix R.requirement Reports 86-24, 86-3 NRR Evaluation Activitie NRR NRR Fire Protection SER PAD-1 Mode 2 SER issued 5/15/8.
Appendix R exemptions PAD-1 Mode 2 Exemptions issued 6/27/8.
Fire Protection Tech. Spec a)
12/17/85 Application PAD-1 Mode 4 Issued 5/30/86; Amendment (PC#136) -
Revised No. 93 TS's for existing equipmen b)
Tech Specs for new PAD-1 9/86 Submitted 5/19/86 with equipment being installe commitment to follow (not a restart item).
c)
Tech. Specs. for new PAD-1 TBD Submitted 5/19/86 with Dedicated Shutdown Syste commitment to follow (not a restart item). Addition of Third Auxiliary NRR Staff review not Feedwater Pum required. Conceptual review done in 198.
TransAmerica-DeLaval PAD-1 Mode 2 Issued 5/27/8 Diesel Interim Authorizatio ATTACHMENT
@on IIT Items)
SCE Action Responsible Due Status/
Item Description Source List N Office Date Completion'Date 6. -Steam Generator Inspection PAD-1 Mode 2 Issued 6/27/8 (License Cond. 3.E)
Submittal provided 3/10/8.
Steam Generator TS 3.16 PAD-1 Issued 6/30/8 Inspection report approva.
Safety Injection System PAD-1 Not required for restar Technical Specification Licensee supplemental Change for Surveillance input provided 6/25/8 of Motor Operated Valves... Seismic Upgrade Safety PBIA Mode 2 Complete SER iss ed Evaluation Report (SER).
7/11/8 Case-by-case study at
.127-31/86 Completed Impel. Case-by-case study at 2/3-4/86 Completed Bechte System case revie /17-21/86 Completed Site inspectio /14-18/86-Inspection completed e,
Receive contractor report /2/86 Issue Seismic SE /19/86 Issue.
Heatup/Cooldown Curves; PAD-1 Mode 4 Issued 5/21/8 PC#137, dated 3/17/8 Amendment #92 1 High Energy Line ISI TS; PAD-1 Mode 2 Issued 5/30/8 PC#160, dated 3/28/8 Amendment #94
ATTACHMENT*on IIT Items)
SCE Action Responsible Due Status/
Item Description Source List N Office Date Completion Date IE Evaluations IE IE 1. Environmental Qualificatio /28/86 Complet Inspection Report 50-206/85-30 issued 2/19/86. Ope items do not affect hardware.