ML20059M892

Intervenor Exhibit I-MFP-40,consisting of Onsite Safety Review Group Apr 1990 Monthly Summary

ML20059M892
Person / Time
Site:	Diablo Canyon
Issue date:	08/18/1993
From:	PACIFIC GAS & ELECTRIC CO.
To:
References
OLA-2-I-MFP-040, OLA-2-I-MFP-40, NUDOCS 9311190424
Download: ML20059M892 (9)

Text

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, PACIFIC GAS & ELECTRIC COMPANY- %gED NNN i DIABLO CANYON POWER PLANT 1 l Onsite Safety Review Group (OSRG) *93 GCT 28 P/; 28 j April 1990 Monthly Sunnary ,

t I Fy:11. 1WW j i The OSRG has reviewed the following items at OSRG meetingWconducted forFa.

j nominally daily basis during the period 3/30/90.through 4/25/90.""During j these meetings, the OSRG Chairman was present and a quorum was* established I i and maintained. Significant-items reviewed are discussed below, and all- l

! items reviewed are listed in Attachment 1. Detailed information on any' l

} item included in this suunary can be obtained by reviewing the." referenced 'l document or by contacting the OSRG.

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J The following items summarize concerns identified by the.0SRG during-the j review period. These concerns have been discussed with appropriate  ;

j personnel, normally the TRG Chairman or responsible department head,-and an 1 j ._ AR has been initiated, if applicable. *

? - . 1. DCO-89-404-N059: Bypassed Quality Control Holdpoints' ,

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This TRG was reconvened to address fourteen additional instances of  :

i bypassed QC holdpoints. The appropriate personnel were not in ,

1 attendance and no analysis of the additional events was performed.

This prevented the TRG from determining if the root causes of these  ;

t instances were encompassed by the root cause' analysis performed for '

j previous occurrences. A' subcommittee will be formed following 2R3 to i analyze how holdpoints are administered and to. develop effective 1 -

corrective actions. The subcommittee is to be comprised-of foreman /QC inspector level personnel.

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. .. l l . 2. OCO-89-RC-N074: SSFAR Concerns With the Control of FeedwaterDuring i i Various Accidents' l -

j The nonconforming condition as determined by the TRG, was thatlthe design basis for mitigating a large break LOCA required maintaining j I st_eam generator water level above the steam generator tubes. -This .

requirement was not included in the Emergency Operating Procedures.'

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I 1 This is an additional example of design basis' information notLbeing i implemented by appropriate Plant procedures.; This NCR does not appear j to have addressed whether there are other design basis requirements which have not been correctly implemented into Plant procedures. .

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However, since the TRGs for NCR DCO-90-TN-N019 are addressing-this

] generic issue, no further OSRG action is planned.

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,; 3. DCO-89-TN-N080: Hydrogen Purge Valve Status Not Properly Controlled.

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j 3 j j The event background information available at the TRG was not of'  !

{ sufficient detail to assess the adequacy of the TRG's root cause- {

j determination. The OSRG believes, however, that the planned corrective  !

l actions adequately address potential event causes.

l 9311190424 930818 PDR ADOCK 05000275.

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OSRG April 1990 Monthly Summary Page 2 of 3 152069 *;

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-152068 l 4. DCl-89-TI-N112: Steam Generator High-High Level following a MFWP Runback Due to a Wiring Error' The TRG was reconvened because it had been noted that the associated

! LicenseeEventReport'(LER 1-89-015) issued for this event contained an

'; inaccurate statement regarding completion of a corrective action. The LER takes credit for briefing I&C:and Electrical Maintenance and for s procedure reviews which were not conducted. The OSRG has initiated'AR 4

A0190182 to document that the LER review process failed to identify the

' inaccurate inforsation.- It should be noted that NCR DC0-89-RC-N062 was:

previously initiated due to the fact that LER 2-88-025 was issued and contained inaccurate statements.

I 5. DC2-90-TN-N015: FH8 Ventilation Inoperable During fuel MovementI This event demonstrates a reduction in the effectiveness of the Quality 1 -.

Evaluation process. A similar event as dccumented in AR.A0175703'

~' occurred on 1/12/90.that involved new fuel movement rather than irradiated fuel moveme-t with.the Fuel Handling Bu11dina boundary; breached, thus there was no Tech Spec' violation... QE Q0007341 for the above AR was initiated on 3/10/90. Had a more timely. analysis been performed, the event described in this NCR might.have been prevented.

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l 6. DCO-90-P91-N022: Notice of Violation on Housekeeping Discrepancies

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-a The OSRG believes that the TRG's root cause determination of

' " procedures not followed" is a symptomatic problem statement which merely restates the reason for the issuance of the NOV; the adequacy of the corrective actions is therefore in doubt,.

The OSRG has. identified the above concerns via the independent

. - , technical review documentation associated with the response.to the NOV.

'~ 7. LER 1-90-003-00: Control Room ESF Actuation on a High Radiation Alarm

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DEe terInadequate'Procedu.res

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i The OSRG realizes that the LER was written due to RE-25 initiating an '

ESF function. However, steam generator blowdown isolation RE-27, did actuate during this event. Even though it.is not an ESF actuation, it should have been included in the event description for two reasons:-

1) to fully and accurately describe the event initiation and consequences,and2) to illustrate.the extent of the lack of adequate evaluation of the=effect of the thimble tube transfer upon installed plant radiation monitors. This concern was documented in our LER independent review. i w% ,

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OSRG April 1990 Monthly Sumary 152069 Page 3 of 3 152068

8. INPO SER 13-89: Multiple Problems Following a Fire Complicate Plant Stabilization, dated 3/13/90, Chron147049.

The OEA response does not address SER Comments 2 and 3 which both basically recomend that Plant procedures be reviewed and modified if necessary to assure that adequate contingency instructions are provided. The OEA response only addresses SER Coments 1 and 4.

This OSRG concern has been included as an AE to AR A0182246 which addresses other OEA responses that do not completely address all issues.

The OSRG continues to monitor Plant activities by conducting Plant tours and surveillance, reviewing the daily Shift Foreman / Control Operator's logs, all significant Action Requests / Quality Evaluations and by attending appropriate Plant TRG, PSRC, Staff, NRC Exit and Scheduling meetings. In addition, DCNs are screened and those having a significant potential impact upon operations are identified for a more thorough review.

Any questions on the above items should be directed to the OSRG Chairman.

WALKER T. RAPP Chairman, OSRG JAStaso(691-4167):jak The signatures below indicate review and concurrence.

A..J. Chitwood //k -

D. D. Christensen )

D. Helete [

B. A. LoConte Ib d dps4 [ -

D. A. Taggart ,T4, ,

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s Attachment 1 152069 .

Onsite Safety Review Group -

j April 1990 Monthly Summary 152068

1. Nonconformances The OSRG either attended TRGs for the following NCRs or if the TRG was not attended, reviewed the completed NCR package. Specific critique coments have been provided to the responsible Chairman and will appear-in the OSRG Quarterly Trend and Critique Summary.

DC2-88-EN-N010:' Steam Generator Blowdown Did Not Isolate-(AMSAC Design)

DC1-88-TI-N091: Unit 1 Reactor Trip on 8/30/88 Due to MFWP l-2 Overspeed Trip l DC2-88-EM-N095: Autostarts of Diesel Generators on Auxiliary to Startup Power Auto Transfer DCO-88-TN-N107: RHR Pumps Fail to Achieve Minimum Recirculation Flow-Rate Requirements 7 DCO-89-TI-N001: Recurring Failures of the Unit I and Unit'2 Main and Bypass Feedwater Regulating Valves and Associated Equipment f

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' DC2-89-WP-NO35: As-Built Configuration of Electrical Raceway Support Not in Accordance With the Design Change Package DCO-89-m-N059: Bypassed Quality Control Holdpoints DCO-89-TN-N061: Required Changes Not Input into AP C-450 DCO-89-TI-N067: Inadequate Setpoint and Scaling Calculation Control

" DCO-89-RC-N074: SSFAR Concerns With the Control.of Feedwater_During ~ , .~ .

Various Accidents "

DCO-89-TN-N080

Hydrogen Purge Valve Status Not' Properly Control, led.

DCO-89-RC-N093: Failure to Implement NRC Commitments

! DCl-89-TN-N096: Moveable Incore Flux Detector System Thimble Tube

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DC1-89-TI-N112: Steam Generator High-High Level following a MFWP Runback Due to a Wiring Error DCO-90-EN-N002: ITT-Grinnell Hydraulic Snubber Could Not Achieve Its

+/-Five Degree Rotation Due to Interference Between Paddle and Welds of Rear Bracket Ears to the Base DC2-90-WP-N004: Scaffolding Seismic Review Deficiency DC1-90-TC-N008: CRVS Shift and Steam Generator Blowdown Isolation Due to Movement of Radioactive Material Above SFP t

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7 DCO-90-M-N013: Crosby Relief Valve Blowdown Ring Settings 152069 DC2-90-EM-N014: Limitorque Spring Pack Relaxation DC2-90-TN-N015: FHB Ventilation Inoperable During Fuel Movement DC2-90-M-N016: Steam Generator Blowdown Line Snubbers found Locked Up DC2-90-EM-N017: RCP Motor Delaminations DC1-90-TN-N018:' Issuance of Notice of Violation for Changing STPs Without Submitting an On-The-Spot-Change DCO-90-TN-N019: Violation of Seismic DesiCn Basis Associated With~.

Water in Containment Spray System Piping DC2-90-0P-N020: PY-21A Voltage Transient Causes CRVS and FHB Ventilation System Mode Changes j T DCO-90-M-N022: Notice of Violation on Housekeeping Discrepancies i I

DC2-90-m-N023: Steam Supply Check Valve to Turbine AFWP Found Stuck. l 3 Open  !

7 2. Regulatory Correspondence i License Amendment Request (LAR) 89-03, Revision of< Technical Specification 3/4.3.1 and Tables 3.3-1 and 4.3-1. Item 23. Seismic Trip, PG&E Letter No. DCL-89-323 dated 12/26/89 Chron142333.

LAR 90-01, Revision of Technical Specification 3.4.2.2_and Associated

'n Bases - Operation with One' Pressurizer Safety Valve Inoperable'and-Disabled, PG&E Letter No. DCL-90 25, dated 1/25/90, Chron144128.

., Response to NRC Bulletin 88-09', Thimble Tube Thinning, PG&E Letter No. DCL-90-094, dated 4/4/90, Chron14 377.

Response to NRC Generic Letter 89-1 , Safety-Related Motor Operated Valve Testing and Surveillance, PG&E Letter.No. DCL-89-324, dated 12/27/89, Chron142455.

Generic Letter 89-1 , Request for Action Related to Resolution of-Unresolved Safety Issue A-47. " Safety Implication of Control Systems in LWR Nuclear Power. Plants," Pursuant to 10 CFR 50.54(f).. dated 9/20/89, Chron138425.

Generic Letter 90-0 ' Relaxation of Staff Position in Generic Letter 83-28 Item 2.2 Part 2 " Vendor In rface for Safety-Related Components," dated 3/20/90, Chron 48023.

Response to Generic Letter 89-1 , PG&E Letter No. DCL-90-075,; dated 3/19/90, Chron147323.- ~

10CFR 50.59 Annual Report of Facility Changes Procedure Changes,-

Tests, and Experiments March 23, 1988 - March 22, 1989, PG&E Letter No.

DCL-90-080, dated 3/21/90, Chron147529.

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Licensee Amendment Request'89-08. Revision of Technicat 152068.'

Specifications 3.1.1.1, 3.1.1.2, 4.1.2.1, 4.1.2.2, 3.1.2.5, 3.1.2.6 and

! Associated Bases -Reduce the Baron Concentration in the Boric Acid System, PG&E Letter No. DCL-90-098, dated 4/10/90, Chron148672.

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i Licensee Amendment Request 90-02, Emergency Technical Specification Change to Technical. Specification 3.4.2.2 - One Time Exemption to i Operate With One Pressurizer Safety Valve Inoperable and Disabled PG&E '

Letter No. DCL-90-048, dated 2/20/90, Chron145584.

3 Issuance of Amendment No. 49 to Facility _ Operating License No.

DPR-80 and Amendment No. 48 to Facility Operating License No. DPR-82, l dated 2/21/90, Chron145804.

NRC Request for_ Additional Information Relating to NRC Staff Review of~  !

Masonry Wall Issues at Diablo Canyon (TAC Nos. 74142 and 74143), dated i 3/20/90, Chron147665. '

NRC Request for Additional Information-Relating to NRC Staff Review of- -I F

Masonry Wall Issues at Diablo Canyon '(TAC Nos. 74142.'and 74143), dated 4/6/90,Chron148600.

NRC Meeting Minutes of 2/16/90 Management Meeting to_ discuss Quality  :

Assurance Performance (associated witn Inspection Report 50-275/90-06  ;

and 50-323/90-06), dated 3/16/90, Chron147689. '

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NRC Acknowledgement of Correspondenc and Receipt of. Fine Associated with Open Sump Access Hatches, dat 4/5/90,Chron148598.

NRC Inspection Notice 50-275/90-0 , 50-323/90-01 dated 4/2/90, Chron148374.

Reply to Noti e of Violation in NRC Inspection Report'Nos. _

" 50-275/89-34 and 50-323/89 34 PGLE Letter No. DCL- -089, dated '

3/30/90,Chron148031.

Reply to NRC Inspection Report Nos. 50-275/89'-33 and 50-323/89-33. PG&E-  ;

Letter No. DCL-90-102, dated 4/16/90, Chron149019. '

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3. Licensee Event Reports LER i Event Date Description /NCR 1-84-042-00 2/20/84 Containment Isolation Valves Not Sealed. Closed Due. -

Misinterpretation of T ch Spec 4.6.1.1.a ~

(NCRDCO-89-TN-N080) 1-90-003-00 2/22/90 Control Room Ventilation F Actuation on High Radia on Alarm due to:Inadequat Procedur~e (NCRDC1-90-TC-N008) y

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1-90-004-00 3/9/90 Technical Specification 3.0.3  !

Entry Due to Personnel Error

.(NCRDC1-90-0P-N011) 152068  !'

2-90-001-00 3/7/90 FHB Ventilation System Shift to Iodine' Removal Mode.Due to. l Inadequate Work Package Preparation and Implementation for a Design Change .

(NCRDC2-90-TI-N010) l

4. Operating Experience Information -

PG&E Response to NRC'I.E.'Information Notice 88-2 . P tential For loss of Post-LOCA Recirculation Capabi..ty Due to Insulat n Debris-  ;

Blockage, dated 3/1/590, Chron147225.

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PG&E Response to NRC I.E. Information Notice.89-0 : Criminal  :

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Prosecution.of Licensee's Former President For Inten onal: Safety Violations, dated 3/3/90, Chron126975.

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PG&E Response to NRC I.E. Information Notice 89-0 :  !

otentia1' Problems

- from the Use of Space Heaters, dated 2/14/90.1Chron 6134.

7 PG&E Response to NRC I.E. Information Notice 89-0 : ent Anchor Bolts' in Boiling Water Reactor Torus Supports, dated 2/23 0, Chron126314.

PG&E Response to NRC I.E. Information Notice 89-  :' edit'for Control ,

Rods Without Scram Capability in the Calculation of e Shutdown Margin, dated 3/21/89,~Chron128016.

PG&E Response to NRC I.E. Information Notice 89-1 : Undetected ,

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Installation Errors in Main Steam Line Pipe Tunnel D fferentlal'- H Temperature - Sensing Elements at Boiling Water Rea ors, dated ,

2/15/89,Chron126130.. l PG&E Response to NRC I.E. Information Notice 89 2.: Changes in Performance Characteristics of Molded-Case Circuit' enkers,'d n ed 8/4/89,Chron134357.

i PG&E Response to NRC 1.E. Information Notice 89-2: Environmental Qualification of Litton-Veam CIR Series Electrica Connectors, dated 3/27/89, Chron127896.

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NRC !.E. Information Notice 89-59, Supplement 1 Su pliers of. i Potentially Misrepresented Fasteners., dated 12/6/89 Chron142059.

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PG&E R'esponse to NRC I.E. Information Notice 89-7 bris in .

Containment' Emergency Sumps and Incorrect Screen Con gurations,-dated 3/14/90 Chron147226.-~ ~ ~ ' - -' ~ " '

PG&E Response to NRC !.E. Information Notice 89-84 Failure of Ingersoll Rand Air Start Motors As'a Result of Pinion Gear Assembly Fitting Problem.s,. dated 3/19/90, Chron147228.

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PG&E Response to NRC I.E. Information Notice 89-8 Type HK Circuit 152069, .

Breakers Missing Close Latch Anti-Shock Springs, at 2/27/90, .

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Chron146277/146680.

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l PG&E Response to NRC I.E. Information Notice;89-8 Recent NRC-Sponsored Testing of' Motor Operated Valves, dated /12/90, Chron145321/145738. <

PG&E Response to NRC I.E. Information Noti e 90-07* New Information Regarding Insulation Material Performance and Deb s Blockage of PWR -

Containment Sumps, dated 3/12/90 Chron1 7228.

INPOSignificant/ventNotification68 Loose Contact Carrier Screws in Sylvania Tyoe/TH Contactors, dated 3/12/90, Chron146848.

INPD SER 13- ultiple Problems Following a Fire Complicate Plant Stabilization, ted 3/13/90, Chron147049.

l INPO SER 19-8 . Multiple Slipped / opped Control Element Assemblies  ;

l Caused by Intermittent Ground, da d 3/16/90, Chron147170/147785. ,

Westinghouse Letter 90PGE-G-0034 egarding Guidance for Measuring MTC, ';

, dated 3/12/90, Chron147549.

Westinghouse Letter PGE-90-543 --Contro Room Safety Injection Block Switches, dated 3/15/90, Chron147227.

~ Westinghouse Technical Bulletin 89-08. . Solid State Protection System I Testing Anomaly, dated 2/12/90, Chron145738/145372.

! 5. Miscellaneous Items tP a) Justification for Continued Operation (JCO) 90-07 Revision 0 for Unit 1. RCP Motor Rotor Delamination,. dated 3/31/90.

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b) JC0 M -05, Revision 0 for Unit 1, limitorque Motor Operator Torque

..- Spring Pack, dated 3/29/90. " ~

., a c) JC0 89-23, Revision 1, Reactor Incore Neutron Monitoring System Thimble Tube Thinni,ng, dated 3/12/90.

d) JC0 89-25 Revision 1. Foreign Object in Containment Recirculation Sump Suction Piping, dated 4/4/90.

e) JC0 89-22. Revision 1. Containment Recirculation Sump Screen i Assembly, dated 4/5/90. '

f) The 1989 Operating Experience Assessment Effectiveness Review was issued 3/30/90, Chron148107. Several recommendations were made as a result of this review and each recomendation is being tracked i and will be implemented via NOS Action Plan 2240.04 "INPO Good l Practices Review." and DCPP Action Plan 3000.03-006 "INPO Self Evaluation 1990."

g) OSRGNonconformance'TrendAnalysik/TRGCritiqueSummaries'were issued for the Fourth Quarter 1989 (dated 4/12/90, Chron148972)~andL First Quarter 1990 (dated 4/12/90, Chron148973).

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f. 6. OSRG Open Items

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Closed 152068 r a) Open Item 086-31, Management Decision Trend Toward Nonconservatism in Event Reporting, is being closed and will be tracked via a similar OSRG Open Item (OI 088-26).

b) Open Item 088-33, Changeout of Eight Pairs of Nested Springs, was closed based on issuance of two DCNs to replace the springs per Westinghouse's design.

Opened l

a) Open Item 090-05, Problems Identified With the New Procedure Approval / Routing Process.

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! Reopened r

a) Open Item 087-14 associated with premature closure of work l . documentation was reopened based on recent additional instances of this type. This Open Item was previously. closed 8/23/89.

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