ML13308A155

From kanterella
Jump to navigation Jump to search
Forwards Systematic Assessment of Licensee Performance Board Review of Facilities for Jul 1981-June 1982.Input Requested
ML13308A155
Person / Time
Site: San Onofre  
Issue date: 07/16/1982
From: Sternberg D
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
To: Chaffee A, Kirsch D, Yuhas G
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
References
NUDOCS 8207230441
Download: ML13308A155 (31)
v • d • e


Text

e 0

s JUL 16 198 MEMORANDUM FOR: D. F. Kirsch, RV I

l T

DESIGNATED ORIGINAL A. E. Chaffee, RV G. P. Yuhas, RV tertified By

,i 1<

W. P. Mortensen, RV R. F. Fish, RV J. H. Eckhardt, RV H. Rood, NRR FROM:

D. M. Sternberg, Chief, Reactor Operations Projects Branch

SUBJECT:

SALP BOARD REVIEW OF SAN ONOFRE UNITS 2/3 (SONGS-2/3)

REFERENCE:

Memorandum to Same Addresses from Sternberg, Same Subject, dated June 10, 1982 As indicated in the referenced memorandum, members of the board are herewith provided with an Input Data Package consisting of the functional areas to be evaluated, evaluation criteria, a summary of inspection activities, an analysis of Licensee Event Reports and enforcement actions issued by this office during the pertod of July 1, 1981 through June 30, 1982. Based upon a review of this material, the results of inspections performed, and/or your observations of licensee performance during the above interva&I you are requested to prepare, for each unit, a brief performance analysis and recommended conclusion (in accordance with NRC Chapter 0516) for each functional area which you or your predecessor has inspected or been involved with.

It is important that this input be forwarded to D. F. Kirsch of this office in time to be reviewed by August 11, 1982.

D. M. Sternberg, Chief Reactor Operations Project Branch bcc:

DMB/Document Control Desk (RIDS) 8207230441 820716 PDR ADOCK 05000361 R

PDR OFFICEO 3URNAME)

KIRSCH S

BERG DATE) 7//(p/82.

7 82 NRC FORM 318(1oso)NRCM e240 fl-iri i

PiRc l copy USGPO:1980-32982,

J UL 171 0

V

-2

Enclosures:

Summary of NRC MC 0516 :

Licensee Activities - Units 2 and 3 :

Inspection Activities - Units 2 and 3 :

Enforcement History - Construction Reactors -

Units 2 and 3 :

Construction Deficiency Reports - Units 2 and 3 :

Enforcement History - Operating Reactors - Units 2 and 3 :

Enforcement History Summary - Units 2 and 3 :

LER ANALYSIS - Unit 2 :

LER and Enforcement Causal Analysis - Unit 2 0:

Investigations and Management Conferences cc:

J. Davis, NMSS C. Michelson, AEOD F. Wenslawski, RV D. Schuster, RV G. Zwetzig, RV J. Crews, RV F. Miraglia, DOL, NRR

pf REGlj UNITED STATES NUCLEAR REGULATORY COMMISSION REGION V 1450 MARIA LANE, SUITE 210 WALNUT CREEK, CALIFORNIA 94596 July 16, 1982 MEMORANDUM FOR:,D. F. Kirsch, RV A. E. Chaffee, RV G. P. Yuhas, RV W. P. Mortensen, RV R. F. Fish, RV J. H. Eckhardt, RV H. Rood, NRR FROM:

D. M. Sternberg, Chief, Reactor Operations Projects Branch

SUBJECT:

SALP BOARD REVIEW OF SAN ONOFRE UNITS 2/3 (SONGS-2/3)

REFERENCE:

Memorandum to Same Addresseesfrom Sternberg, Same Subject, dated June 10, 1982 As indicated in the referenced memorandum, members of the board are herewith provided with an Input Data Package consisting of the functional areas to be evaluated, evaluation criteria, a summary of inspection activities, an analysis of Licensee Event Reports and enforcement actions issued by this office during the period of July 1, 1981 through June 30, 1982. Based upon a review of this material, the results of inspections performed, and/or your observations of licensee performance during the above interval, you are requested to prepare, for each unit, a brief performance analysis and recommended conclusion (in accordance with NRC Chapter 05161 for each.

functional area which you.or your predecessor has inspected or been involved with..

It is important that this input be forwarded to D. F. Kirsch of this office in time to be reviewed.by August 11, 1982.

D. M. Sternberg, Chief Reactor Operations Project Branch DESIGNATED ORIGINAL Certified By July 16, 1982

Enclosures:

Summary of NRC MC 0516 :

Licensee Activities - Units 2 and 3 :

Inspection Activities - Units 2 and 3 :

Enforcement History - Construction Reactors -

Units 2 and 3 :

Construction--Deficiency Reports - Units 2 and 3 :

Enforcement History - Operating Reactors -

Units 2 and 3 :

Enforcement History Summary - Units 2 and 3 :

LER ANALYSIS -

Unit 2: :-LER and,Enforcement Causal Analysis - Unit 2 0:

Investigations and Management Conferences cc:

J. Davis, NMSS C. Michelson, AEOD F. Wenslawski, RV D. Schuster, RV G. Zwetzig, RV J. Crews, RV F. Miraglia, DOL, NRR Page 1

SUMMARY

OF NRC MC 0516 Functional Areas to be Evaluated (Per NRC Manual Chapter 0516, Section 043)

a. Operational and preoperational Reactors (1) Plant operations (2) Radiological controls (a) radiation protection (b) radioactive waste management (c) transportation (d) effluent control and monitoring (3) Maintenance (4) Surveillance - includes inservice and preoperational testing (5) Fire protection (6) Emergency preparedness (7) Security and Safegurads (8) Refueling -

includes initial fuel loading (9) Licensing activities (10) Others (as needed)

b.

Construction Phase Reactors (1) Soils and foundation (2). Containment and other safety-related structures (3) Piping systems and supports -

includes.welding, NDE and preservice inspection (4) Safety-related components -

includes vessel, internals, pumps (5) Support systems -

includes HVAC, radwaste, fire protection (6) Electrical power supply and distribution (7) Instrumentation and control systems (8) Licensing activities (9) Others (as needed)

Page 2 II. Evaluation Criteria (Per NRC Manual Chapter 0516, Section 044)

The evaluation criteria are as follows:

(1) Management involvement in assuring quality (2) Approach to resolution of technical issues from safety standpoint (3) Responsiveness to NRC initiatives (4) Enforcement history (5) Reporting and analysis of reportable events (6) Staffing (including management)

(7) Training effectiveness and qualification Guidance for using these criteria to arrive at a category assignment is contained in the Appendix to NRC Manual Chapter 0516.

Page 3 III.

Performance Categories (Per NRC Manual Chapter 0516, Section 042)

Performance categories are defined as follows:

Category 1. Reduced NRC attention may be appropriate. Licensee management attention and involvement are aggressive and oriented toward nuclear safety; licensee resources are ample and effectively used such that a high level of performance with respect to operational safety or construction is being achieved.

Category 2. NRC attention should be maintained at normal levels.

Licensee management attention and involvement are evident and are concerned with nuclear safety; licensee resources are adequate and are reasonably effective such that satisfactory performance with respect to operational safety or construction is being achieved.

Category 3. Both NRC and licensee attention should be increased.

Licensee management attention or involvement is acceptable and considers nuclear safety, but weaknesses are evident; licensee resources appear to be strained or not effectively used such that minimally satisfactory performance with respect to operational safety or construction is being achieved.

Each functional area evaluated will be assigned one of the categories defined above. The Appendix to NRC Manual Chapter 0516 lists a number of attributes for each evaluation criteria. The final performance category assigned to each functional area. evaluated should be a composite of the performance categories assigned to each-evaluation attribute tempered with judgement.

Page 1 LICENSEE ACTIVITIES Unit 2.

The Unit was granted a Facility Operating License, Number NPF-10, on February 16, 1982, authorizing operation up to five percent power.. Initial fuel loading began on February 19, 1982, and was completed on February 28, 1982.

Since February 28, 1982, the licensee has been engaged in post core load preoperational testing. The licensee has experienced a total delay of about 1.5 months in the post core load preoperational test program due to the following:

Clean up of boric acid in containment due to water flow out of instrument port.

Removal of the reactor vessel head to retrieve foreign material which was inadvertently dropped into the vessel by a workman

  • through an instrument port.

Repair of check valves which caused excessive reactor coolant system leakage.

Repair of Auxiliary Feedwater pump motors to replace motor bearings.

Evaluation and resolution of excessive instrument noise on safety related instruments.

Replacement of reactor coolant pump seal packages on all reactor coolant pumps.

The licensee has completed all required TMI modifications on schedule with only a.

few items remaining to be complete. The region has reason to believe that the remaining items will be completed-on schedule.

Page 2 LICENSEE ACTIVITIES Unit 3 The licensee is in the final phases of plant construction and is well into the pre-core load preoperational test program. Construction of the unit is about 96 percent complete and-the pre-core load preoperational test program is about 55 percent complete.

Page 1 Unit 2 INSPECTION ACTIVITIES DN 50-361 Inspection Activities No. of Inspections Manhours

a. Regional Inspection
1. Routine Operations Inspection 7

738

2.

Reactive Operations Inspection 0

0

3.

Routine Construction Inspection 6

291

4.

Reactive Construction Inspection 1

78

b.

Resident Inspection (Mostly Operations) 9 870

c. Health Physics
1. Routine Inspection 8

528

2.

Reactive Inspection 0

0

3. Health Physics Appraisal 0

0

d. Environmental
1. Routine 4

60

2.

LER Follow-up 0

0

e. Security and Safeguards
1..Routine 5

916

2. Reactive 0

0

f.

Emergency Preparedness

1. Routine 1

102

2. Reactive 0

0

3. Emergency Preparedness Appraisal 2

230 TOTAL 43 3,813 Page 2 Unit 3 INSPECTION ACTIVITIES DN 50-362 Inspection Activities No. of Inspections Manhours

a.

Regional Inspection

1. Routine Operations Inspection 1

31

2. Reactive Operations Inspection 0

0

3. Routine Construction Inspection 11 367
4.

Reactive Construction Inspection 0

0

b.

Resident Inspection 3

233 (Mostly Operations)

c.

Health Physics 0

0

1.

Routine Inspection

2.

Reactive Inspection

3. Health Physics Appraisal
d.

Environmental 0

0

1.

Routine

2.

LER Follow-up

e.

Security and Safeguards 0

0

1.

Routine

2.

Reactive

f. Emergency Preparedness
1.

Routine 0

0

2.

Reactive 0

0

3. Emergency Preparedness Appraisal 1

183 TOTAL 16 814 Page 1 NATUREAND NUMBER OF VIOLATIONS -

CONSTRUCTION REACTORS UNIT 2

DOCKET NO.

50-36 FUNCTIONAL INSPECTION VIOLATIONS (SEVERITY LEVEL) REPORT NO.

AREA MAN HOURS VI V

IV III II I

DEVIATION SOILS AND FOUNDATION 0

CONTAINMENT AND OTHER SAFETY RELATED STRUCTURES PIPING SYSTEMS AND SUPPORTS INCLUDES WELDING, NDE AND 0

PRESERVICE SAFETY RELATED COMPONENTS INCLUDES VESSEL, INTERNALS, 8

AND PUMPS SUPPORT SYSTEMS -

INCLUDES HVAC, RADWASTE, FIRE 84 81-32 PROTECTION ELECTRICAL POWER SUPPLY AND DISTRIBUTION 11 81-34 INSTRUMENTATION AND CONTROL SYSTEMS 20 LICENSING ACTIVITIES 0

OTHERS (List)

a. Quality Assurance 6
b. Design 34
c. Bulletins, 50.55(e)

Reports, Followup 206

Items, and Independent inspection TOTAL 369 1

Page 2 NATURE AND NUMBER OF VIOLATIONS -

CONSTRUCTION REACTORS UNIT 3

DOCKET NO. 50-362 FUNCTIONAL INSPECTION VIOLATIONS (SEVERITYLEVEL)

  • REPORT NO AREA MAN HOURS VI V

IV III II I

DEVIATION SOILS AND FOUNDATION 0

CONTAINMENT AND OTHER SAFETY RELATED STRUCTURES 82 PIPING SYSTEMS AND SUPPORTS INCLUDES WELDING, NDE AND 48 PRESERVICE SAFETY RELATED COMPONENTS INCLUDES VESSEL, INTERNALS, 25 82-11 AND PUMPS SUPPORT SYSTEMS -

INCLUDES HVAC, RADWASTE, FIRE 0

PROTECTION ELECTRICAL POWER SUPPLY AND DISTRIBUTION 35 INSTRUMENTATION AND CONTROL SYSTEMS 8

LICENSING ACTIVITIES 0

OTHERS (List)

a. Quality Assurance 2
b. Design 8
c. Bulletins, 50.55(e) Reports, Follow-up>Items, and 159 Independent Inspection TOTAL:

367 1

Numbers indicate NRC Inspection Report Number.

S 0 Page 1 50.55(e) ITEMS (Units 2 and 3)

INTERIM FINAL NOTIFICATION REPORT REPORT DATE DESCRIPTION OF CONDITION DATE DATE 07/10/81 Shock arrestors-omission of lockwire.

NA 08/05/81 07/15/81 Steam generator feed ring distortion.

NA 08/11/81 07/23/81 Dresser safety valves - EPRI test failure.

08/20/81 10/30/81 08/03-81 Flammable spray adhesive - electrical use.

NA 09/01/81 08/03/81 (P)

Diesel generator camshaft bearing.

NA 09/01/81 08/17/81 (P)

Cracked guide lug inserts..

NA 09/16/81 09/10/81 (P)

General Electric HEA relays.

NA 10/02/81 (N R) 09/15/81 Use of incorrect welding procedure.

NA 10/14/81 09/15/81 Pipe support wrapper materials certified NA 10/13/81 as stainless steel but determined to be incorrect.

09/15/81 (P)

Failure of safety-related equipment to NA 10/14/81 remain in an emergency mode after reset (NR) of the ESFAS signal.

09/23/81 (P)

Incorrect wire connectors on radiation NA 10/23/81 monitors.

10/06/81 (P)

Pressurizer level indicator malfunction NA 11/05/81 due to condensate in flexible tubing.

10/23/81 (P)

Preservice examination UT indications in NA 12/04/81 RPV.

11/03/81 (P)

Magnetrol switches in flooding sensor system.

NA 12/02/81 11/12/81 (P)

Misorientation of Unit 2 core support barrel.

NA 12/09/81 01/08/82 (P)

LPSI flow valve actuator coupling.

NA 01/21/82 02/04/82 03/09/82 (P)

Sigma Lumigraph indicators - resister failure. NA 04/05/82 (See Unit 2 LER 82-09)

Page 2 50.55(e) ITEMS (Units 2 and 3)

INTERIM FINAL NOTIFICATION REPORT REPORT.

DATE DESCRIPTION OF CONDITION DATE DATE 04/23/82 (P)

Main steam dump to atmosphere valves.

NA 05/20/82 06/21/82 Core protection calculator - wiring from CRD cabinets to CPC.

(Not reportable for Unit 2) 06/22/82 Gas radiation monitors - detector leakaae and calibration.

NOTES:

P - Potential NR-Not reportable

NATURE ANOUMBER OF VIOLATIONS -

OPERATI REACTORS Page 1 SAN ONOFRE UNIT 2

FUNCTIONAL INSPECTION VIOLATIONS (SEVERITY LEVEL)*REPORT NO.

AREA MAN HOURS V

IV III II 82-15

1. Plant Operations 478 82-20 2-15 02-20
2.

Radiological Controls

a.

Radiation Protection 183

b. Radioactive Waste 345 Management
c.

Transportation 0

d. Effluent Control 60 and Monitoring
3. Maintenance 80
4.

Surveillance -

includes 549 Inservice & Preoperational Testing

5. Fire Protection 0
6. Emergency Preparedness 332
7.

Security and Safeguards 916

8. Refueling - includes Initial 70 82-15 Fuel Loading
9.

Licensing Activities 0

10. Other
a.

Quality Assurance -

148 82-12 Program & Implementation

b.

TMI Action Items 285 TOTAL 3,446 1

5

NATURE AND NUMBER OF VIOLATIONS - OPERATING REACTORS Page 2 SAN ONOFRE UNIT 3

DOCKET NO.

FUNCTIONAL INSPECTION VIOLATIONS (SEVERITY LEVEL)*

AREA MAN HOURS V

IV III II

1. Plant Operations 48
2.

Radiological Controls 0

a. Radiation Protection 0
b. Radioactive Waste Management 0
c.

Transportation 0

d. Effluent Control 0

and Monitoring

3. Maintenance 0
4.

Surveillance -

includes Inservice & Preoperational 209 Testing

5. Fire Protection 0
6.

Emergency Preparedness 183

7. Security and Safeguards 0
8. Refueling - includes Initial 0

Fuel Loading

9. Licensing Activities 0
10. Other 7
a. Quality Assurance Program & Implementation 0
b.

TMI Action Items 0

TOTAL 447

Numbers indicate NRC Inspection Report Number.

ITEMS OF NONCOMPLIANCE 0 Page 1 Docket No. 50-361 NRC INSPECTION SEVERITY DESCRIPTION REPORT NO.

LEVEL Failure to completely seal off air spaces around four cable penetrations.

(Failure of OC personnel to pro 50-361/81-32 DEVIATION*

perly inspect penetrations as required by procedures)

Failure to document removal of a Class IE conduit 50-361/81-34 VI*

after the conduit had been inspected and accepted.

(Failure to follow procedures)

Failure to comply with administrative controls 50-361/82-12 IV +

governing temporary modifications.

(Failure to follow procedures)

Failure to verify engagement of CEA extension 50-361/82-15 IV+

shaft coupling.

(Failure to follow procedures)

Failure to comply with operating licensee condition 50-361/82-15 IV governing use of overtime for operating personnel (Personnel Error)

Failure to submit monthly operating report by the 50-361/82-20 V+

date required in technical specifications.

(Failure of management control system)

Failure to comply with tech. spec. action statement 50-361/82-20 IV regarding the supply power for two 120 VAC vital instrument busses from alternate shources.

(Personnel Err Cause of violation in parenthesis

+NRC Enforcement -Policy; 10 CFR 2, Appendix C, 47 FR 9987, dated March 9, 1982.

ITEMS OF NONCOMPLIANCE Page 2 Unit 3 Docket No.

50-362 NRC INSPECTION SEVERITY DESCRIPTION REPORT NO.

LEVEL As-built configuration of shutdown heat exchanger

-upper seismic restraints did not conform to drawing 50-362/82-11 IV +

requirements.

(Failure to follow procedure)

INRC Enforcement Policy, 10 CFR 2, Appendix C, 47 FR 9887, dated March 9, 1982.

Page 3 ESCALATED ENFORCEMENT ACTIONS DN50-361/362 Units 2 and 3

a.

Civil Penalties -

None

b.

Orders -

None.

C. Confirmatory Action Letters -

None Page 1 LICENSEE EVENT REPORTS (Unit 2)

TABULAR LISTING TYPE OF EVENTS:

a.

Personnel 12

b.

Design/Man./Constr./Install.

5

c.

External cause 0

d.

Defective procedure 3

e.

Component failure 3

x.

Other 0

TOTAL 23 Licensee Event Reports Reviewed:

Report Nos. 82-01 through 82-25 CAUSAL ANALYSIS Six sets of common mode events were identified;

a.

LERs 82-03 and 82-08 identified unplanned dilutions of the reactor coolant system boron concentration. The failure to include the Refueling Water Storage Tank outlet valve bypass valves on the plant drawing, and corresponding failure to assure these bypass valves were included in valve line-up sheets, is a contributory cause.

b. LERs 82-04, 82-13, 82-17, and 82-20 involved missed or inadequate surveillance tests caused by inadequate procedures (one LER) or personnel error (three LERs).
c.

LERs 82-11, 82-16, 82-24, and 82-25 involved failure to comply with.

Technical Specification Limiting Condition for Operation Action statements due to personnel error (three LERs) or defective procedures (one LER).

Page 2

d. LERs 82-12 and 82-19 involved the inoperability of the control room emergency air cleanup system. The failure to initially identify a design error was a causative factor in the occurrence of the second event.
e. LER's 82-01, 82-07, and 82-23 involved the inadvertent actuation of the water spray fire protection.system due to personnel error.
f. LER's 82-10 and 82-14 involved inadequate installation of fire rated assemblies and fire barriers. The failure to perform adequate and comprehensive inspections following the initial identification of inoperable fire rated assemblies (see Special Report dated March 29, 1982) is a contributing factor for these LERs.

TABUM LISTING OF LERs BY FUNCTIONA'KREA Pg Unit 2 3

Docket No.

FUNCTIONAL AREA NUMBER/CAUSE CODE TOTAL

1. Plant Operations 5/A, 2/B, 2/D, l/E 10
2.

Radiological Controls None 0

3.

Maintenance 1/A

4. Surveillance -

includes Inservice & Preoperational 4/A, 1/B, 1/D, 2/E 8

Testing

5.

Fire Protection 2/A, 1/B 3

6. Emergency Preparedness
7. Security & Safeguards
8. Refueling -

includes Initial Fuel Loading

9. Licensing Activities
10. Other
a. Quality Assurance Program

& Implementation 1/

CAUSE CODES:

A -

Personnel Error B - Design, Manufacturing, Construction, or Installation Error C -

External Cause D -

Defective Procedures E - Component Failure X - Other LICENSEE EVENT REPORTS (LERs)

.Page 4

LISTING Unit 2 Docket No. 50-361 APPARENI CAUSE TYPE DESCRIPTION LICENSEE LER ANALYSIS Destruction of charcoal filter beds due to 82-01 30 Day flooding caused by failure of deluge valve Personnel Error Personnel Error to act as an isolated valve.

82-02 24 Hour Inadvertent loss of shutdown cooling system Personnel Error Defective Procedure flow while in mode 6..

82-03 24 Hour Unplanned dilution of RCS while restoring Personnel Error De efaleuproce o

de bypass valves on Ow ings and in valve line lip prorediir Failure to perform required weekly 82-04 30 Day surveillance on containment purge Personnel Error Personnel Error isolation system.

Failure of control room emergency air 82-05 30 Day cleanup system to start when required.

Defective Procedure Defective Procedure 82-06 30 Day Stratification of boron concentrations in Design Error Design Error RWST No. T006 due to inadequate mixing.

82-07 30 Day Inadvertent initiation of water spray fire Personnel Error Personnel Error S protection system in control bldg cable riser area.

Failure to include 82-08 24 Hour Unplanned dilution of RCS boron concentration Component Failure bypass valves on drw ings and in valve line up procedure.

Defective Procedure Potentially faulty indication on 41 safety 82-09 24 Hour related sigma lumigraph indicators due to Design Error Design Error incorrectly specified resistors.

LICENSEE EVENT REPORTS (LERs)

Unit 2 Page 5 LISTING Docket No. 50-361 APPAREN( CAUSE LER NO.

TYPE DESCRIPTION LICENSEE LER ANALYSIS Inadequate determination of inoperable fire Failure to adequately rated assemblies and corresponding inadequate Personnel Error inspec fire rated assembies (see Specia 82-10 24 Hour fire watch assignments.

Report of 3-29-82)

Failure to operate control room emergency air 82-11 24 Hour clean-up system in emergency mode when both Personnel Error Personnel Error channels of control room airborne monitoring are discovered inoperable.

Train B of control room emergency air cleanup 82-12 30 Day system determined to be inoperable during Component Failure Component FailureW performance of monthly surveillance test.

Reactor Coolant System leak rate determined 82-13 30 Day to.be in excess of technical specification Defective Procedure Defective Procedure allowable.

Failure to a dequahel y Improperly sealed refractory blankets on inspect fire rately 82-14 24 Hour cable tray fire barrier penetrations.

Construction/Installa-assemblies (see S ecia tion Report of 3-29-82' Overspeed trip of diesel generator 2G003 82-15 30 Day during monthly operability test.

Component Failure Component Failure Two vital 120 VAC busses energized from 82-16 24 Hour alternate sources in violation of technical Defective Procedure Defective ProceduW specifications.

82-17 24 Hour Failure to verify adequacy of ESFAS response Personnel Error Personnel Error times prior to entry into Mode 3.

82-18 Cancelled LICENSEE EVENT REPORTS (LERs)

Unit 2 Page 6 LISTING Docket No.

50-361 APPARENi CAUSE LER NO.

TYPE DESCRIPTION LICENSEE LER ANALYSIS Trains A and B of control room emergency air Management failure to cleanup system determined to be inoperable properly evaluate 82-19 30 Day during performance of monthly surveillance Design Error cause of LER 82-12 test.

82-20 24 Hour Failure to perform containment airlock Personnel Error Personnel Error operability surveillance test each 72 hr.

Motor driven auxiliary feedwater (AFW) pumps, 82-21 24 Hour safety injection override relay contacts Construction Error Defective procedure were miswired.

under construction 82-22 CANCELLED 82-23 30 Day Inadvertent actuation of sprinkler deluge Personnel Error Personnel Error system.

AFW system: Motor driven auxiliary 82-24 24 Hour feedwater pump discharge valve inoperable Personnel Error Personnel Error due to incorrect setpoint.

AFWS: Steam driven AFW PMP P140 declared 82-85 24 Hour inoperable resulting in removal of two Personnel Error Personnel Error auxiliary feedwater pumps from operable statut.

82-26 82-27 SPECIAL REPORTS Unit 2 Page 7 Docket No. 50-361 EVENT DESCRIPTION TECHNICAL EVENT LETTER REC'D IN APPARENT SPEC.

DATE DATE REGION CAUSE Establish firewatches on all At OL Unit 3 under const. and Unit 3 is inoperable fire rated assy.

3.7.9.a Issuance 3-29-82 04-01-82 under Unit 2 fire protection-system.

UPDATE 4-23-82 04-26-82 UPDATE 5-14-82 05-21-82 Blankets in cable trays (LERs 82-10, 82-14 UPDATE 6-11-82 06-14-82 Failure to perform adequate inspection on turnover to station.

SDCS relief used to mitigate RCS pressure transient 3.4.8.3,1.C 05-07-82 6-07-82 06-10-82 Inadequate operating procedure Page 1 CAUSAL ANALYSIS ENFORCEMENT AND LERs SAN ONOFRE UNIT 2 Docket No. 50-361 CAUSE CATEGORY ENFORCEMENT LER TOTAL ACTIONS ANALYSIS Failure of Management or Management Control System 1

3 4

Failure to Follow Procedure 4

4 Defective Drawing or Procedure 1

7 8

Personnel Error 2

9 11 Design/Construction/Manufacturing/

0 2

2 Installation Error Component Failure 0

2 2

TOTAL 8

23 0

Page 1 Unit 2 INVESTIGATION AND ALLEGATIONS REVIEW DN 50-361 One formal investigation was conducted during this period consisting of 78 inspector-hours onsite. This investigation dealt with allegations regarding improper activities involving the installation of foam fire barriers.

Several of the allegations were either partially or fully substantiated.

Information developed during this investigation resulted in the identification of one enforcement action (Deviation:

Failure to assure penetration fire stops completely seal off air around cable penetrations; NRC Inspection Report No. 50-361/81-32).

0 Page 2 Unit 3 INVESTIGATION AND ALLEGATIONS REVIEW DN 50-362 None.

0 Page 3 MANAGEMENT CONFERENCES HELD DURING APPRAISAL PERIOD Units 2 and 3 Management Meeting, September 1, 1981 This meeting was held to discuss the results of NRC's regional evaluation of licensee performance (SALP), regarding activities authorized by NRC License No. DPR-13 and NRC Construction Permits Nos. CPPR-97 and 98, during the period of June 1, 1980 through June 30, 1981.

Retrieved from "https://kanterella.com/w/index.php?title=ML13308A155&oldid=5227907"