ML17298A237

SALP Data Package for Jul 1981 - Feb 1983,including Excerpts of NRC Manual Chapter 0516,summaries of Licensee Activities & Insps,Enforcement actions,10CFR50.55(e) Repts & Other Pertinent Data.Results to Be Provided After 830413 Meeting

ML17298A237
Person / Time
Site:	Palo Verde
Issue date:	04/30/1983
From:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
To:
Shared Package
ML17298A236	List: ML17298A235 ML17298A237
References
NUDOCS 8303140555
Download: ML17298A237 (42)

Text

ENCLOSURE 1

U.S.

NUCLEAR REGULATORY COMMISSION REGION V SYSTEMATIC ASSESSMENT OF LICENSEE PERFORMANCE PAIO VERDE NULCEAR GENERATING STATION APRIL 1983 8303i40555 830308 PDR ADOCK 05000528 6

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II 1I TABLE OF CONTENTS II f

Introductio'n

'ummary of Results Criteria e

Performance Analysis O~eretieee

~ 0.1.

0. 2'.

0.3.

0.4.

0.5.

0.6.

0.7.

0.8.

'Plant Operations

'<<Radio3.ogical Controls Maintenance Surveillance Fire Protection Emergency Preparedness Security and Safeguards Refueling Construction C.1.

C.2.

C.3.

C.4.

C.5.

C,6.

C.7.

C.S.

Soils and Foundations Containment and Other Safety Related Structures Piping Systems and Supports Safety Related Components Support Systems Electrical Power Supply and Distribution Instrumentation and Control Systems Licensing Activities V.

Supporting Data and Summaries l.

2.

3e 4.

5.

Construction Deficiency Reports Licensee Activities Inspection Activities Enforcement Actions Management Conferences TABLES Table 1A Table 18 Table 2

Table 3

Table 4

Table 5

Table 6A Table 68

.Deleted Deleted Reportable 10 CFR 50.55(e)

Reports Inspections Conducted Summary of Inspection Activities Enforcement Items Enforcement Summary - Operations Enforcement Summary - Construction

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INTRODUCTION Pu ose and Overview The Systematic Assessment of Licensee Performance (SALP) is an integrated NRC staff effort to collect the available observations on an annual basis and evaluate licensee performance based on those observations with the objectives of improving the NRC Regulatory Program and 'Licensee performance.

'III.

The assessment period is July 1, 1981 through February 28, 1983.

This assessment contains pertinent observations of NRC and licensee activities.

Evaluation, criteria used during this assessment are discussed in Section III.

Each criterion was applied using the "Attributes for Assessment, of Licensee Performance" contained in NRC Manual-Chapter I0516 I

n

SUMMARY

'OF RESULTS

The summary of results willie provided in narrative form after the Board meeting., Data'ill be=put in table form on Tables 1A and 1B Region V Form 107.

u CRITERIA n

1 The following,evaluation criteria were applied to each functional area:

1.

Management involvement in assuring quality.

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2.

Approach to 'resolution of technical issues from a 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.

To provide consistent evaluation of licensee performance, attributes associated with each criterion and describing the characteristics applicable to Category 1, 2, and 3 performance were applied as discussed in NRC Manual Chapter 0516, Part II and Table 1.

The SALP Board conclusions were categorized as follows:

~Cate or 1:

Reduced NRC attention may be appropriate Iicen.aee management attention and involvement are aggressive and oriented toward nuclear safety; licensee resources are ample and effectively

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used such that a high level of performance with respect to operational safety or construction is being achieved.

~Cate or 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.

~Cate or 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 appeared strained or not effectively used such that minimally satisfactory performance with respect to operational safety and construction is being achieved.

IV.

PERFORMANCE ANALYSIS - Jul 1

1981 - Februar 28 1983 0.

Operations O.l Plant 0 erations (Prep erational Testin

)

0.2. Radiolo ical Controls 0.3. Maintenance 0.4. Surveillance 0.5. Fire Protection

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0;7.

,0.8.

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C.2.

Emer enc Pre aredness r

Securit

.'and Safe uards R~eiuelin t

I Construction

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Soils and,'Foundations s

Containment and Other Safety Related Structures I

C.3. Piping System and Supports I I 1

C.4. Safety Related Components C.5. Support Systems C.6. Electrical Power Supply and Distribution C.7. Instrumentation and Control Systems C.8. Licensing Activities

-'To be completed by responsible personnel designated in the cover rqemorangum.

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V.

SUPPORTING DATA AND SUMMARIES 1.

Construction Deficienc Re orts (CDR's)

CDR's submitted as reportable 10 CFR 50.55(e) items during the reporting period are listed in Table 2.

Table 2 provides the dates of the initial notification and the written report.

The table also provides a description, the Arizona Public Service (APS) Deficiency Evaluation Report (DER) number, the functional

area, and the status of NRC inspection, open (0) or closed (C).

2.

Licensee Activities To be provided by Vorderbrueggen.

3.

Ins ection Activities Inspection activities for the SALP period are provided in

,tabular form.

Table 3 lists the inspections conducted during the SALP period.

,Table 4 provides a breakdown of NRC inspection manhours utilized 'at the three sites.

4 Enforc'ement Actions

't There were no escalated enforcement actions during the SALP

', period.

)(

Items of noncompliance issued during the SALP period are listed in Table 5.

Tables 6A and 63 provide a summary of items of noncompliance for the operations functional areas and the const'ruction'functional areas respectively.

tl 5.

Mana ement Conferences One management conference was held during the appraisal period which dealt with the SAIP subject of regulatory performance.

That. was"the 1981 SALP meeting held October 16, 1981 (described in repor't 50-528/81-17).

Other management meetings were held as described below.

July 8-9, 1981 - NRC management visit to the site to review the status of construction and to present the NRC inspection program for preoperational and startup testing and subsequent plant operation.

October 13, 1981 - A meeting was held at the NRC Region V Office in Walnut Creek, California at the request of the licensee to discuss their actions involving three

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construction deficiencies reported under 10 CFR 50.55(e).

,The defi'ciencies involved discontinuities in vendor supplied pipe spool welds, p'ipe elbow welds and failures in embed'late bolts.

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Verbal Notif.

Date

'/12/81 6/18/81 e

7/2/81 Written Rhett e

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'Final

'10/21/81

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'7/30/81 TABLE 2 REPORTABLE 10 CFR 50.55(e)

REPORTS Descri tion APS'unctional DER Area No.

f, Electrically operated 81-16 C6 circuit'reakers, contain a

,bearing which may deform.

Pullman Powe'r Products did 81-17 C3 not,provide the required weld joint'reparation on. pipe supp'or t,s.,'"

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Co'nt'r'ary: to ASME IXI 81-20 C3 requirements, pipe support drawings for piping lugs require fillet welds in lieu of full penetration welds.

NRC Ins ection 7/15/81 ll/3/81 9/10/81 Final Certain Agastat. relays have 81-22 C6 10/21/81 a premature time out condition.

Final Unit 2 Fuel Building roof 81-29 C2 ll/25/81 truss bolts elongate before reaching required torque value.

Final Limitorque Valve Operators 81-31 C3 10/15/81 require replacement of shaft keys.

10/7/81 12/3/81 Final 5/20/81 Final 12/30/81 Void in backfill under Unit 1 81-35 Cl Auxiliary Building due to break in temporary line.

Unit 1 Safety Injection 81"46 C3 System 8" motor operated valve by Borg Warner may fail as installed horizontally per design.

12/15/81 Final 12/15/81 Final Unit 2 Diesel Generator has a 81-48 C6 defective cylinder head.

NSSS Water I.evel Transmitters 81-49 C7 may give erroneous readings due to variations of water leg.

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Verbal Notif Date Written R~eoit 1/5/82 Final 7/6/82 12/30/81

Final, 5/24/82 n

0 Punctional NRC Area

~Ina ection C7 81-57 C6 e

Description, APS DER No.

Unit" 1 tfain Control"Panel violates 81-53

"',.',sepa'ration requirements'or class 1E "and nonclass wiring.

n Type.HMA Relays -have excess uninsulated leads which could cause short circuits.

2/22/82 Final 3/23/82 3/3/82 Final 7/23/82 3/26/82 Final 6/8/82 4/7/82 Final 7/7/82 4/15/82 Final 7/14/82 Diesel Generator Lube Oil Strainer 82-3 Baskets require replacement.

Instrument

'clamp drawings do not 82-4 show locknuts required by ASME III.

Instrument clamps were installed 82-12 without calculations for thermal expansion and seismic requirements.

Unit 1 and 2 Instrument installa-82-14 tion bolting was used without issue control required by AS1iE.

Pipe supports are installed in 82-15 Unit 1 with invalid heat numbers; not traceable.

C7 C7 C7 C7 C3 7/7/82 Final 8/6/82 7/13/82 Final 11/15/82 Diesel Generator Control Panel 82-36 wiring not crimped into terminal lugs.

Class lE wiring crimped with less 82-37 pressure than specified due to lack of maintenance program for crimp tools.

C7 C6 0

8/6/82 Final 12/28/82 Unit 1 Instrument.

AC circuit 82-40 C7 breakers were left set below allowable trip range after testing.

0 8/2/82

'Final ll/23/82 7/9/82 Interim 8/9/82 GE Switchgear in Unit 3 has loose 82-41 wires due to improperly crimped termination lugs.

Reactor Coolant Pump Pressure Tap 82-42 nozzle weld leak due to overheating stainless alloy.

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Date 8/13/82 Written R~eo rt Final 2/7/83 i.'f

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>>'-- NRC DER Area"

." ~Ins'ction 4

Main Control Panels in Unit"2rhave 82-43 C7 improperly crimped termination lugs.

8/13/82 8/26/82 Zinal 12/7/83 Final 11/15/82 Load centers in Units 1, 2, 3 have 82-k4 improperly crimped termination lugs.

Safety Injection System Valves 82-45 installed with motor operators not qualified for inside containment.

C6 C3 C

9/1/82 Final 12/7/82 9/8/82 Final 10/8/82 Instrument line check valves seized open by welding heat.

82-48 Unit 1 Steam Generator has pipe 82-49 support incorrectly welded to sway struts instead of approved brackets.

C7 C3 C

0 9/30/82 'inal 2/22/83 Unit 1 Main Steam Valves have internal corrosion from exposure while removed for system hydro-static test.

82-54 C3 0

9/30/82 Zinal 2/22/83 DC Motor feeder cable sizing may 82-55 C6 not provide sufficient voltage at full load.

0 10/15/82 Final 12/28/82 10/21/82 Final 11/22/82 Auxiliary feedwater valves are 82-57 C3 carbon steel instead of stainless, purchase error.

Diesel generator high voltage 82-58 C6 cubicles and foundations have bolts on 3 sides, but seismic qualification test used 4 sides.

0 10/21/82 Final 11/22/82 Unit 3 diesel generator piston has 82-60 C6 nonconforming material certification.

0 11/24/82 Final 12/23/82 Unit 1 Refueling Water Storage 82-75 C3 Tank Suction Strainers improperly secured due to oversize bolt holes.

12/17/82 Final 1/17/83 12/22/82 Final 1/19/83 1/18/83 Final 2/16/83 Diesel gen voltage reg.

sys. trans.83-1 may not perform at high temperaturesk C6 Improperly crimped termination 82-78 C6 lugs in Unit 2 Water Chillers.

Mechanical Shock Absorbers do not 82-82

, C3 permit 5 degree movement.

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TABLE 3 INSPECTIONS CONDUCTED (7/1/81 - 2/28/83)

PALOS VERDE NUCLEAR GENERATING STATION Unit 1 50"528

~Re ort No.

81"09 Unit 2 50-529 R~eort No.

81-09 Unit 3 50"530 81-09 7/6-7/10/81 Regional Construction Areas Piping, containment post tensioning instrumentation electrical 81-10 6/9-7/10/81 Regional QA and admini-strative controls 81-12 81-10 7/8-7/9/81 Regional Operations 8/17-8/21/81 Regional Construction Management Visit Reactor Vessel internals, con-crete, structural steel, electrical, preservice inspec-tion, pipe supports 81-13 81-11 8/3-8/31/81 81-11 7/8-7/30/81 e

f Resident Operations Resident Construction Training, staffing, preoperational testing.

Components, post-tensioning, piping, structural steel 81-15 81-16

'1-17 81-13 81-12 81-13 8/3-9/4/81 9/1;9/30/81 10/6/81 Resident Construction Resident Operations Regional and Resident Post tensioning, internals, piping, pipe supports structure Preoperational

testing, QA, maintenance, training SALP Meeting 81-18 81-19 81-14 81-14 o

10/13/81 Regional 10/19-10/23/81 Regional Radiation Meeting regarding piping and structural bolts Radiation protection chemistry, training

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Unit 2 50-529 R~eort No.

Unit 3 50"530

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Areas 81-20 81-15 81-15 10/5-10/30/81 Regional Construction Piping, structural

steel, components concrete electrical instrumentation, preservice e

81-21 81-22 10/1-10/30/81 11/2-11/30/81 Resident Operations Resident 8 Regional Operations Preoperational test-ing, maintenance startup testing, QA Preoperational test-

ing, QA, training 81-23 81-16 9/28-10/31/81 Resident Construction

Piping, components, liner welding penetrations 81-24 81-17 81-17 11/2-12/4/81 Resident Construction Internals installa-tion, piping, supports 81-25 12/1-12/24/81 Resident Operations Startup testing, QA, test equipment 82-01 1/4-1/24/82 Resident Operations Startup testing, QA 82-02 82-01 82-01 1/25-1/29/82 Regional Construction Instrumentation, structural steel welding as built configuration 82"03 82-02 82-02 1/4-1/29/82 Resident Construction Piping, penetrations, concrete 50.55(e) items 82-04 2/1-2/19/82 Resident Operations Startup testing, main-tenance and calibration TMI actions 82-05 2/16-2/19/82 Regional Radiation TID Placement,

staffing, training 82-06 1/2-2/5/82 Regional Operations Procedures,

staffing, safety committee, QA 82-07 82-03 82-03 2/1-2/26/82 Resident Piping, liner welding, Construction electrical records 50.55(e) items

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Unit 1 Unit 2 50-528

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':,82-04 82"09 I

Unit 3 50-530 R~o'rt No.

82-04

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3/1-,4/2/82 'esident IN Construction 3/22;4/30/82 Resident Operations Areas Electrical, 50.55(e)

Reorganization, pre-requisite testing, preoperational testing.

82-10 82-05 82-05 3/29-4/2/82 Regional Construction Electrical, components, Bulletins and Circulars 82-11 82-12 82-13 82-06 82-06 5/10-5/14/82 Regional Radiation 4/5-4/30/82 Resident Construction 5/3-5/28/82 Resident Operations Radiation protection, chemistry, environmental protection, training Piping, electrical, penetrations, instrumen-tation 50.55(e) items Preoperational

testing, gA, Maintenance 82-14 82-07 82-07 5/3-6/25/82 Resident Construction Piping, Reactor Vessel and Steam Generator Insta1lation, 50.55(e) items 82-15 82-16 82-17 82-18 82-08 82-08 4/26-4/28/82 Regional Operations Cancelled 5/11-5/14/82 Regional Construction 6/8-6/10/82 Regional Operations Procedures, training Structural welding, pipe welding Procedures, safety committee 82-19 82-20 6/1-6/25/83 Resident Operations 7/6-7/7/82 Regional Radiation Preoperational

testing, training Radiochemistry 82-21 82-22 7/1-7/16/82 Resident Operations 7/17-8/20/82 Resident Operations Startup testing, maintenance Startup testing, train-ing, maintenance, gA 4

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50-528 R~eort No.

82-23 82-24 Unit 2 50-529 R~eort No.

Unit 3 50-530

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8/23-9/17/82 Resident Operations 9/27-10/1/82 Regional Radiation Areas Startup testing, maintenance, QA Radiation protection, training, radwaste

system, Circulars and Notices 82-25 82-26 82-27 82-09 82-10 82-09 82-10 82-11 8/2-8/6/82 Regional Construction 8/30-9/3/82 Regional Construction 7/13-9/3/82 Resident Construction 9/20-10/15/82 Resident Operations Liner welding, pipe pipe supports Pipe Supports, welding welding Grouting, post tension-ing, penetrations piping, electrical,50.55(e)items Startup testing,

(}A, maintenance training 82-28 82-29 82-30 82-31 82-32 82-33 82-11 82-12 82-12'I>>

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4 9/13-10/8/82 Resident Construction 10/4-10/8/82 Regional Construction e

t10/18-11/19/82 Resident Operations o

.11/15-11/19/82 Regional Construction 11/18-12/17/82 Resident Operations 11/22-12/17/82 Resident Operations Post tensioning, electrical, 50.55(e)

Electrical, components structural welding Startup testing, design

changes, QA preopera-tional testing, SG Chemistry Heat treatment,,

Bulletins and Circulars Prerequisite testing Design changes, preop-erational testing, piping verification 82-34 10/12-11/19/82 Resident Components, penetrations, Construction pipe welding, 50.55(e) items

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Unit 1 50-528 R~eort No.

Unit 2 50-529 R~eort No.

Unit 3 50"530

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Areas 82-35 12/16-12/23/82 Regional Containment SXT, ILRT Construction 82-36 12/8-12/10/82 Regional Operations Procedures 82-37 82-38 82-15 82-16 11/22-12/30/82 Resident Allegations in HVAC, Construction SIT, penetrations 12/20/82-1/21/83 Resident Startup testing,

ILRT, Operations QA, fuel receipt, TMI Items 83-01 83-02 83-03 83-01 83-01 1/4-1/7/83 Regional Operations 1/4-1/17/83 Regional Construction 2/14-2/18/83 Regional Radiation

Records, training Allegations in piping and welding Haterial License, environmental, preopera-tional testing, radiation protection 83-04 83"05

'"NOTE:, Add 83-02 1/24-2/18/83 Resident Operations 83-03 83-02 1/10-'2/28/83 Resident Construction e

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I Eckhardtls allegation 'inspection when published.

Startup testing, maintenance Allegation followup, piping, hangers, 50.55(e),

Bulletin, Tendon Sleeve Repair Unit 2

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TABLE 4

SUMMARY

OF INSPECTION ACTIVITIES (7/1/81-2/28/83)

PALO VERDE NUCLEAR GENERATING STATION A~ctivit rl v

A. Construction,

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1. Resident

2. Region B. Operati'ons

1. Resident

2. Region v

rr, Manhours'nit 1

'06

358, 2663 259 Manhours Unit 2

,382 198 22 0

Manhours Unit 3 352 155 0

0 C. Radiological Safety,

.145 D. Safeguards

,,'0 E. Emergency Preparedness 0

F. Office of Investigations Total Region 2

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2 0

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Inspection R~eort No.

50-528/81-12'~

50-529/81-10:"

Failure to'ollow, procedural moisture" controls, for weld filler metal.

Lunc'h found in weld rod oven.

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'g'ABLE 5 ENFORCEMENT ITEMS,(7/1/81 - 2/28/83) e

.PAIO VERDE NUCLEAR GENERATING STATION

" Severity Unit

~Reb ett Ievel A licabilit Functional Area C.3 Construction-Piping Systems and Supports 50"528/81-12:"

50-529/81-10>"

Failure to follow procedure for access control for fuel pool area (housekeeping)

VI 1/2 C.2 Construction-Con-tainment and other Safety Related Structures 50-528/81 Failure to follow procedure V

Insufficient sized washer on slotted hole in structural steel

, C.2 Construction-Con-tainment and other Safety Related Structures 50-528/82 Omission of fillet welds on V

structural steel required by drawing C.2 Construction-Con-tainment and other Safety Related Structures 50-528/82-09 50-528/82-09 50"528/82-10 50-529/82-05 Excessive debris in battery charger rooms and in remote shutdown. cabinet, area (housekeeping)

Temporary modification tags V

not installed on certain systems where safety valves had been removed and temporary vents had been installed Failure to follow procedure V

for rework of electrical conduit support 0.6 Operations-Maintenance 0.1 Operations-Preopera-tional testing C.6 Construction-Electrical Power Supply and distribution

-Severity levels for inspection report 82-02 and earlier are in accordance with the NRC's Interim Enforcement Policy 45 FR 66754 (October 7, 1980) which provided six severity levels.

Severity levels after 82-02 are in accordance with the NRC Enforcement Policy (10 CFR Part 2 Appendix C) 47 FR 9987 (March 9, 1982), which provides five severity levels.

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Inspection R~eort Mo.

50-528/82-12 50-529/82-06

~Rub eot Severity Ievel Pipe ends not capped contrary V

to procedure Unit Functional C.3 2

Construction-Piping Systems and Supports 50-528/82-25 Control room panels not 50-529/82-09 welded to floor plates per drawing requirements IV C.j Construction-Instrumentation and Control Systems 50-528/82-25 Acceptability of work per-formed without calibration welding machine evaluated as required by procedure.

C.3 Construction-Piping Systems and Supports 50-528/82-30 50-528/83"02 50-528/83-02 Water used in unplanned fill V

of steam generator no.

1 did not meet chemistry specifi-cations Unauthorized, undocumented V,

weld installed in radio-active drain line I

Pipe supp'orts not provided for radioactive drain line (engineering omission) a<

~L 0.1 Operations-Preoper-ational testing C.3 Construction-Piping Systems and Supports C.3 Construction-Piping Systems and Supports e

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Severity Levels I'I

, III IV V

VI 2

'. Plant Operations, (Preoperational

'testing)

2. Radiological, Controls

3. Maintenance

4. Surveillance 5.'ire Protection

6. Emergency Preparedness

7. Security and Safeguards

8. Refueling TABLE 6A OPERATIONS ENFORCEMENT

SUMMARY

(7/1/81-2/28/83) 1

• AIOVERDE NUCIEAR GENERATING STATION-UNIT 1-

, Oper'ations,',

Functional 'Area Total 0

0 0

0 0

0 Totals 0

0 0

0 3

0

"Units 2 6 3 are not listed, there were no Operations items of noncompliance given.

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TABLE 6B CONSTRUCTION ENFORCEMENT

SUMMARY

(7/1/81-2/28/83)

PALO VERDE NUCLEAR GENERATING STATION Construction Functional Area

1. Soils and Foundations Unit 1 Unit 2 Unit 3 Severity Xevels XX XII IV V

VI Total 0

0 0

2. Containment and Other Safety Related Structures Unit 1 Unit 2 Unit 3 2

1 1

3 1

0 Piping Systems and Supports Unit 1 Unit 2 Unit 3

4. Safety Related Components Unit 1 Unit 2

/nit 3 2

1 2

1 3

3 0

0 0

0 5.

6.

7.

8.

Support. Systems Unit., 1

'Unit 2,.

-Unit,',3 ';

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Electrical'.Power,"

'uppl'jf Distribution Unit 1

'nit,2 Unit-3 I'nstrumentationand Control Systems Unit 1 Unit 2 Unit 3 Licensing'ctivities Unit 1 Unit 2 Unit 3 TOTALS 0

0 0

0 0

0 1

0 1

0 0

0 0

0 0

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