ML20247G338

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Forwards Summary Rept for Regional Evaluation of Palo Verde Unit 2
ML20247G338
Person / Time
Site: Palo Verde, 05000000
Issue date: 10/28/1985
From: Martin J
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
To: Harold Denton
Office of Nuclear Reactor Regulation
Shared Package
ML20244B854 List:
References
FOIA-89-226 NUDOCS 8909190041
Download: ML20247G338 (1)


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'J 0CT 2 31905 MEMORANDUM FOR:

Harold R. Denton,. Director l

i Office of Nuclear Reactor Regulation FROM:

J.'B.

Hartin, Regional Administrator Region V

SUBJECT:

PALO VERDE NUCLEAR GENERATING STATION UNIT 2 OPERATIONAL READINESS REPORT (MC 94300)

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This letter transmits the first Region V report sunnarizing the readiness of l

L Palo Verde Unit'2 for issuance of a Low Power Operating License. At present, l-the number of items which require. resolution by the licensee and review by the l-Region V staff is too large to permit a recommendation that.a license be

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issued.

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It is anticipated that.in approximately two weeks, sufficient work will have been accomplished by the licensee and reviewed by the staff to significantly reduce the number of outstanding items.

The information contained in this report will be updated by Region V at a l

l later date as the number of outstanding items is reduced and the unit more 4

l closely approaches readiness for fuel. load.

Orir,intSi?F 1 D Jchn D.f& lif' J. B. Martin

}

Regicnal Administrator

Enclosure:

'As stated cc w/ attachment:

J. Taylor, IE J. Davis, NMSS H. Thompson, NRR T. Novak, NRR G. Knighton, NRR r

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SUMMARY

. REPORT l:

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1 jf REGIONAL EVALUATION

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1 PALO VERDE UNIT TWO-

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DOCKET NO. 50-529 1

PREPARED BY i

U.S.' NUCLEAR REGULATORY COMMISSION REGION V OCTOBER 10, 1985 b

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a.

Summary Status 1.

Applicant's current estimated licensing date:

11/1/85 2.

Inspection Program: Will be completed prior to 11/1/85 provided licensee has reviewed required preoperational test results through the Test Working Group level.

j 3.

Review of Actions on Generic Correspondence: The licensee has not completed action on two Circulars. The licensee's action on each of

)

these and the one remaining Bulletin must be reviewed prior to OL i

issuance. The three Generic Letters will be reviewed as part of l

routine inspection and are not tied to licensing.

4.

Reportable 10 CFR 50.55e Events: All remaining.10 CFR 50.55(e)

I reportable Deficiency Evaluation Reports (DERs) will be reviewed for f

licensee action by RV by November 1, 1985. A sample of the

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remaining Not Reportable DEPs will be reviewed by Region V for deportability assessment by November 1, 1985.

5.

Preoperational Testing: As of 10/8/85, the licensee had completed i

155 of 184 required preoperational tests. Preoperational testing l

will be completed on all safety related or important to safety 1

systems prior to fuel load.

6.

Significant System Performance Deficiencies: All system performance deficiencies appear to have been satisfactorily resolved by the licensee except as noted in Section 1(5). Region V will verify this i

prior to OL issuance.

7.

System Turnovers: 66 of 457 safety related or important to safety subsystems have not been turned over to the operations department.

l I

Approximately 1245 construction deficiencies remain as of 10/8/85.

Region V will begin reviewing this list once it has been reduced to a few hundred items.

8.

Procedures: The surveillance procedures, and with minor exceptions, the operating procedures to be used at Unit 2 are the same as those for Unit 1 except for Unit designation. Seventeen surveillance procedures and three operating procedures remain to be converted l

for Unit 2 use.

b.

Readiness for Operation The following specific issues require resolution.

It is anticipated that some portions of these will be resolved ss license conditions or prior to issuance of the low power license. This dist.inction will be made once the actual low power OL date becomes clear, and the licensee substantially completes the other open items discussed in this report.

1.

The post accident sampling system will not be operational by the present fuel load schedule. Based on past experience, inspection of system may be desirable prior to issuance of the Unit 2 OL in part i

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because the licensee recently submitted an FSAR change for the PAb3 system design.

2.

.The radiation monitoring system test program vill not be substantially complete by the projected fuel load date. The licensee'has stopped preoperational testing and transferred g

responsibility for completion of testing to the operations engineering organization. The test schedule developed shows that testing will be phased in as the monitors are required by Technical Specification.

3.

Testing of the radioactive waste systems (CR, LR, SR) is expected by the licensee to be completed by October 20, 1985 with an additional

'3 to 5 days to review test results and prepare the report.

4.

The pressurizer safety valves acoustic monitoring system must be calibrated.

5.

Approximately twelve allegations are being reviewed by the Region V staff. These allegations are expected to be addressed prior to OL issuance..There is also an allegation related to Radiation Monitoring System startup testing that is unresolved:and may impact on our readiness evaluation.

6.

Loss of auxiliary spray due to loss of charging pumps must be addressed for Unit 2 for adequate corrective action by the licensee.

7.

L'oss of offsite power due to multiplexer malfunction must be addressed by the licensee for Unit 2 as well, c.

Project History Palo. Verde Nuclear Generating Station Unit No. 2 PLANT CHARACTERISTICS:

Docket No.:

05000529 CP No. & Date Issued:

CPPR-142/05-25-76 CP Expiration Date:

12/31/85 Applicant:

Arizona Public Service Company Plant Location:

36 miles west af Phoenix, AZ IE Region:

V AE:

Bechtel NSSS:

Combustion Engineering Constructor:

Bechtel Reactor Type:

PWR DER (MWE):

1304

IN o,.

KEY PERSONNEL:

Corporate

Contact:

E. E. Van Brunt, Jr., Executive V a: President Corporate Address:

P. 0.. Box 52034 Phoenix, Arizona 85072-2034

- Corporate Phone No. :

(602) 271-7900

- NRC LPM:

E. Licitra IE Resident Inspector:

R. Zimmerman/G. Hernandez FUEL LOAD DATE CHANGES AS REPORTED BY UTILITY:

Reason for Change

- Report Date New Schedule Reperted by Utility 11/13/84

'12/31/85 Because Unit 2 construction is sequential to that of Unit l', the Unit I construction..

delays impacted on the Unit 2 construction schedule.

LOCAL PUBLIC DOCUMENT ROOM:

Phoenix Public Library 12 East McDowell Road Phoenix, Arizona 85004 l

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Status as of 10/8/85 d.

CONSTRUCTION STATUS REPORT NUCLEAR POWER PLANTS PALO VERDE 2 CONSTRUCTION STATUS:

Applicant's Current Estimated Fuel. Loading Date:

By 11/1/85 Applicant's Previous Estimated Fuel Loading Date:

10/1/85 Applicant's Estimated Fuel Loading Date at CP 1ssuance:

11/1/84 Applicant'u Current Estimated Commercial Operation Date:

4/86

. Applicant's Construction Completion Estimate as Defined in CP:.

(Earliest) :

2/1/83 (Latest):

12/31/85 CURRENT ESTIMATED PERCENT CONSTRUCTION COMPLETE:

99.9%

COMMENTS REGARDING CURRENT CONSTRUCTION STATUS:

ESTIMATED ACTUAL ESTIMATED ACTUAL ESTIMATED START START COMPLETION COMPLETION % COMPLETE Mobilize and Prepare Site:

6/76 6/77 100%

Plate Structural Concrete:

8/77 12/81 100%

Install Reactor Pressure 6/80 7/80 100%

Vessel:

Install Lar'ge Bore 9/78 5/85 100%

Process Pipe:

Install Large Bore Pipe 10/78 5/85 100%

Hangers, Restraints, and Snubbers:

Install Small Bore Pipe:

4/79 10/85 99.6%

Install Cable Tray:

G/78 3/82 100%

Install Exposed Metal 1/78 10/85 99.9%

Conduit:

Install Power, Control.

2/81 10/85 99.5%

' Instrumentation, and Security Cable:

Install Electrical 5/81 10/85 99.1%

Terminations:

Conduct Reactor Cold 10/84 11/84 100%

Hydrostatic Test:

Conduct Hot Functional 6/85 8/85 100%

Test:

Conduct Preop and 3/83 10/85 88%

Acceptance Tests Necessary for Fuel Load:

e.

NRC Inspccuion Activities MC 2512 Program Status Priority 1 Complete MC 2513 Program Status (Modules Remaining to be Completed)

Module Subject Status 35744 QA Program - Design Changes and Modifications 50%

35745 QA Program - Surveillance Testing 75%

35750

'QA Program - Test and Measurement Eq.

0%

75%

36301 Operational Staffing 0%*

70322 Engineered Safety Features Test 70326 Loss of Offsite Power Test 0%*

0%*

70329 Preoperational Test Verification 0%

79501 Water Chemistry Control 79502 Plant Systems Affecting Water Chemistry 0%

80521 Environmental Protection 0%

83524 External Exposure Control 60%

83525 Internal Exposure Control 60%

84522 Solid Waste 40%*

85%

84523 Liquid Waste 85%*

84524 Cas Waste

  • Indicates action remaining to be done by the licensee.

The modules listed above are scheduled for completion b7 November 1, 1965 with the exception of 35750, which is scheduled for a Palo Verde team inspection October 28 - November 8, 1985. This area was extensively reviewed per the same module in Unit 1 and the M&TE program applies to all operational units.

The Region V Safeguards preoperational inspection was conducted October 4 - 10, 1985. Several violations (related to Unit 1) and open items were identified. Further evaluation of the inspection findings will be necessary and the Safeguards section is not prepared to render an OL recommendation at this time.

The Emergency Preparedness preoperational inspection was conducted on September 27 - October 4, 1985. No open items were identified, however, there will be several improvement items. The improvement items will not affect licensing.

Inspection of TMI Action Plan items is about 75% complete for items required for fuel load. The remaining fuel load items will be reviewed by Region V by November 1, 1985. Seven items still require licensee action.

MC 2514 Program Statur The Limited inspection has been performed for the startup testing phase.

startup test procedures for Unit 2 will be the same as those used in

Unit 1,. The licenses is in the process of converting the Unit 1 test procedures for use in Unit 2.

Special Inspection Activities See Table 1.

fable 1 Insp.

Insp~

Insp' Brief Number Date' Hours Description Findings 81-02 1/26/81-356' Regional Receiving inspectors; equipment 2/5/81 Construction: maintenance. special handling Assessment requirements, maintenance and Team (CAT) storage. appeared weak.

Inspection Management and-QA/QCLvisibility was high; construction management appeared-strong.

'83-07 6/1/82-206 Investigation Allegations substantiated 3/11/83 of allegations (Civil Penalty issued) concerning records safety-related electrical terminations.

84-41

.9/5-12/

384 As-built No significant problems 14/84 configuration identified, control for pipe supports.

Design control administration and implementation.

f.

Generic Correspondence The licensee has satisfactorily responded to all applicable Bulletins and Circulars, with the following exceptions:

(1) IE Bulletin 79-14 (2)

IE Circulars 80-09 and 81-14 The review of the above Circulars is pending licencee completion of action on them. Review of licensee action on Bulletin 79-14 will be completed by Region V by November 1, 1985.

g.

Enforcement History Escalated Enforcement Action Reason for Action Corrective Action Civil penalty of $40,000 dated Unit 1 Electrical Licensee December 12, 1983 (imposition Termination demonstrated that suspended pending release of installation cards other controls on report of investigation by did not reflect termination cards Department of Justice. Report crimp tool number ensured all released by DOJ 20 Sept 84) and signature of terminations were the installer.

technically adequate. This action also applieu to Unit 2.

Civil ' penalty of $40,000 Licensee's Quality Licensee stopped (mitigated to $20,000) dated Assurance program

testing, December A?., 1983 did not maintain conducted a adequate control comprehensive over activities audit of startup affecting quality. work controls, and revised administrative controls for startup testing.

l Proposed Civil penalty of $50,000 Unit 1 Post-Pending dated October 8, 1985 Accident Sampling program was inadequate.

Uncorrected Violations or Unresolved Items Licensee responses to four violations and one unresolved item have not been reviewed as of 10/8/85. Review of those items requiring licensee action prior to fuel load will be completed by November 1, 1985.

e h.

Licenses and contractor Initiated stop Work Actions Licensee Initiated Stop Work Actions Year Organization Reason / Period Corrective Actions 1978 Bechtel Radial bends did not meet Rework tag prepared in drawing requirements. Re-compliance with WPP/QCI pairs started without NCR 54.0 As-built survey record or repair instructions docu-attached to NCR. NCR mented. (12/13/78-12/15/78) issued C-Y-1078 (12/14/78) 1979 Dechtel ASME code acceptance cri-Test data and results ob-teria not met for ultra-tained for acceptance of sonic testing.

(7/31/79-double welded stainless 8/11/79) steel pipe.

1981 Sechtel and Insulation being deformed to Deforming of insulation CE to fit between Reactor analyzed and accepted.

Vessel and RV support col-Caps minimized.

uans and technical justi-fication not provided for assurance of quality and in-tegrity of system not vio-lated.

(5/5/81-5/21/81) 1981 Dechtel Procedures / instructions or Procedure initiated and PCN controls not developed to written to WPP/QCI 28.0 control the connection and charging of batteries to assure safety of personnel and equipment.

(8/31/81--

9/1/81) 1981 Dechtel Five Star Grout 150 used and Authorization for use de-does not meet required leted from 13-CM-365.

strength.

(12/14/81-4/28/82) 1982 APS Operations Control of temporary elec-90AC-0Z2.11 identified as trical jumpers, temporary procedure for Startup to lifting of terminal leads, uset 73AC-92205 was re-temporary change of set-vised to be in effect only points and use of temporary at fuel load.

modification not being per-formed in accordance with 73AC-9ZZO5 but in accordance with 90AC-CZZll.

(4/1/82-4/2/82)

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Year Organization Reason / Period Corrective ActAons Tendons stored without west-All tendons discussed in-

  • 1982' Bechtel ber protection. (5/18/82-spected, rust removed and 5/21/82) recosted. No signs of pit-ting or other deficiency.

Considered acceptable and covered with plastic.for weather protection.

Western Concrete personnel reinstructed in require-ments for storage of tendons.

1982 Bechtel Stopped installation of Issue of DCP 1SN-SQ-001, masple supply lines to air Rev. 5.

Existing system

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installed in accordance radiation monitors as sup-with current revision of ply sample lines are not designed to requirements of design drawing. Problem ANSI N13.1 Seat 55.

resolved on QAF82-45.

(5/27/82-6/29/82) complete inventory taken, Material accountability not r

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1982 Bechtel bt.ing maintained in Zone III controlled access material srea established for this.

and tool log updated.

Re-work. (6/2/82-6/2/82) moved section pipe spool and inspected. Area in-spected, personnel in-structed.

Procedure cancelled which BPC will review WPP-QCI 1982 Bechtel governs BPC preparation for 31.0 and write PCN; review area transfer / release. Re-Fire Astriers, Cable Iray quirement for inspection /

Covers and Conduit Sealant and incorporate into exist-acceptance of cable tray ing procedures or add to covers and barriers dele-ted. ' Requirement for in-WPP/QCI 31.0 J

I spection/ acceptance of un-scheduled commodities has been deleted as was commit-ment to verify installation /

inspection documentation with-l in scope of area transfer.

f (7/20/82-7/22/82)

Test Director not certified Test Director will be fa-as qualified for test MG300, miliarized with the pro-1982 APS Startup FPN PD2.

(7/11/82-7/22/82) cedure and familiarization will be documented. QC to be present during test.

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Year Organization Reason / Period Corrective Actions j

1982 APS Startup Circuit breaker removed 90GA-0ZZ28 revised and j

without permission and no Maintenance will assure clearance was requested nor that personnel are aware issued.

(8/4/82-8/4/82) of station clearance re-quirements and test con-duct requirements.

I 1982 BPC Startup Pailure to: respond in a Corrective actions agreed and APS timely manner to OINs; to on by Bechtel and APS QA.

Maintenance implement requirements of AD-112 with regard to M&TE usage logs and forms; to re-spond to calibration overdue notices; to comply with ANSI N45.2.16, Section 3; provide an adequate response to CAR 82-036.

(9/17/82-9/18/82) 1982 Maintenance Work Order 482 & 483 issued Procedure initiated in ac-to set safety valves did not cordance with code and provide adequate instruc-specifications. Special tions to perform the work instructions issued with as required by code, ASME work orders.

Section II.

(10/14/82-11/21/82) 1982 APS and Valves SGN-HV-05 and SGN-HV-Performed required actions Bechtel 06 were stroked over a two of steam generator re-Startup hour period and allowed sp-covery plan.

proximately 100,000 gals.

of highly contaminated H O 2

into the secondary side of SG1 and at the time SG2 was unknown. Isolation valves for j

nitrogen purge thought to be closed were open.

(10/19/82-10/19/82) 1983 APS Startup Cleanliness of Low Pressure Inspection to determine and Safety injection System was amount of damage and veri-

~~ perations indeterminate and continued fication of cleanliness.

O operation without corrective Potential causes for entry action could lead to signi-of foreign material into ficant damage to LPSI pumps. system investigated.

On-(1/18/83-1/19/83) going inspections and evaluation of system cleanliness.

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4 Year Organization

_ Reason / Period Corrective Actions 1983 APS Startup Startup and Maintenance Per-90AC-0ZZO2 and 90GA-0ZZ28 Operations sonnel were not performing were revised and require a work activities in accord-review of tdt's prior to ance with approved project rework or installation of procedures.

(2/8/83-3/4/83) materials on "Q* class com-ponents to determine if an NCR should be written of if it is reportable. All TER's written 1/17/83-2/11/83 to be reviewed.

1983 Bechtel Typical drawings in FCR DCP issued providing ne-71577E differ signifi-cessary drawing clari-cantly from actual field fication.

conditions and bolts could be installed incorrectly.

Original field conditions will become indeterminate if bolts are installed without adequate directions.

(11/21/83-4/14/84) 1983 Bechtel Deportability evaluation in DCPs were transmitted to question. If skewed T Resident Engineering for joints do not affect safety deportability review.

Con-why are welds being re-dition not reportable.

paired?

(11/23/83-12/20/83) 1983 Combustion Personnel records do not inspectors performed demon-Engineering provide documentation of stration of proficiency.

certification of inspectors.

(11/28/83-12/2/83) 1983 innryeo, Inc.

Contract PV83-8215 Specifi-Program was reviewed and fication 83-95.71-06-001 did approved.

did not adequately in-pienent the.spp11 cable technical and quality re-quirements which must be in-posed on Inryeo as a result of the scope of work inryco

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is to perform.

(12/16/83-12/30/83) 1

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s Beebtel Initiated Stop Work Actions Year Organization Reason / Period Corrective Action 1973. Shurtleff &

E-7018 weld rod not stored Drying ovens obtained from Andrews in drying ovens. (6/17/77 Bechtel. SDDR issued.

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-6/17/77) 1978 Peabody Test.

Penetrant materials not Materials tested satisfac-analyzed.

(1/12/78-1/27/78) torily, procedures revised.

1978 Construction Unauthorized M-6 solvent SAR Change Notice 814 is-used for cleaning.

sued to define qualifica-(2/10/78-3/16/78) tion parameters. WPF/QC1 14.0 revised.

1979 Construction Youngstown pipe material is Radiograph accomplished -

suspect - DER 79-4 no defects found.

(5/18/79-6/22/79) 1979 Clark Painting Unacceptable curing opera-Construction NCP.s issued.

tions Supplier QA program in-(11/5/79-11/8/79) provements initiated.

1980 Construction Rockbestos Class II cable supplier and Bechtel con-i may have unqualified trols implemented. Cable

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splices. DER 80-4 qualified, any cable with j

i (3/5/80-10/24/80) repairs is approved for outside containment only.

1980 Construction HPSI suction pump piping Piping arrangements were may not be acceptable to determined acceptable.

pump supplier. DER 79-13

/

(3/28/80-11/14/80) 1980 Construction ITT Grinnell pipe supports Acceptable - based on Code were received with under-Inquiry, ASME File No.

site fillet welds. DER 8D-6 NI-77-406.

(4/25/80-7/8/80) 1980 Construction Certain cable pulling stop-Condition acceptable based ped due to potential de-on engineering analysis.

ficiency in Containment re-bar detailing. DER 80-19 (6/30/80-10/18/80)

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YEAR ORGANIZATION REASON / PERIOD CORRECTIVE ACTION 1980 Construction Unit 3 shell concrete Condition acceptable based 3

placement stopped based on engineering analysis.

on 80-SW-4 and DER 80-19.

(6/30/80 - 10/17/80) i 1980 Construction Unit 2 anchor bolts for Design change implemented.

4 seal table are Condition corrected.

1 inadequately imbedded -

f DER 80-16 (7/3/80 - 10/22/80) 1980 Construction Deficiencies on Whiting NCRs issued, procedures polar crane and improper revised, training conducted.

processing of Bechtel documents.

(10/16/80 - 11/3/80) 1981 Construction Concrete placement Condition acceptable based deficiencies - SI tank. on engineering analysis.

DER 80-24 (10/17/80 - 2/2/81) 1981 M.M. Sundt/

Concrete truck mix not NCRs issued and preventive Tanner Co.

properly monitored action implemented.

enroute.

(11/13/80 - 11/14/80) 1981 Reliance Truck QA program deficiencies Audit findings resolved.

Company found during audit by Supplier QA Manager Bechtel replaced.

(2/17/81 - 8/11/81)

'1981 Construction Ultrasonic by Peabody NCR issued. WPP/QCI 12.0 not witnessed by Bechtel revised to clarify Level II or III requirement.

(2/25/81 - 3/10/81) 1981 Construction Construction Startup NCRs issued, procedures testing accomplished issued.

without formal procedural control.

(5/13/81 - 5/21/81) 1981 Construction Bolts failed due to NCRs issued. Bolt testing incorrect hardness, program accomplished. Refer

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DER 81-14 to DER 81-14.

(6/15/81 - 7/6/81) i l

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." YEAR OECANIZATION REASON / PERIOD CORRECTIVE ACTION 1981.

Otis Elevator Welding Program not Welding of brackets-approved by Bechtel.

affected. Bechtel walkdown (10/8/81 11/16/81) determined welds acceptable. Supplier will use Bechtel controlled filler material.

1981 Marathon Stcol Supplier lack of control Procedures developed and for subcontracted NDE - implemented.

field erected tanks.

Initiated 12/10/81 -

Closed.7/21/83 upon completion of reverification activity.

1982 Comsip Supplier veld SDDR 3236 issued - Comsip deficiencies on main weld procedure revised, control panels - at supplier's facility.

(4/12/82 - 5/27/82) 1982 Construction Grouting procedure to Condition corrected to meet accomplish DER 81-35 QA program requirements.

disposition not approved or controlled.

(8/17/82 - 8/20/82)-

l 1983 Construction Engineering procedure Approved QC procedure for repair of crack in 1seued.

l spray pond does not address QC participation..

1 (5/17/83 - 5/20/83) 1983 Construction Site process sheets for Review cycle modified, QA installation of Unit 3 review accomplished.

reactor vessel internals not submitted for QA approval.

1983 Construction QA overview of pipe Reinspection conducted.

1 support reinspection QA reverification program j

program identified implemented to require unacceptable weld monthly overview of weld conditions not found by activities.

QC. DER 83-74 (12/2/83 - 12/12/83) 1

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f.

YEna ORGANIZATION REASON / PERIOD.

CORRECTIVE ACTION' 1984 Engineering Validation program of Documents were issued 14ich HVAC duct supports by meet QA program Engineering and supplier requirements.

does not meet QA. program requirements.

(3/2/84 - 3/8/84) 1934 construction-Items. removed during condition corrected.

authorized replacement Procedures revised to activities were not~

clarify requirements.

properly identified and controlled.

(5/3/84 - 6/8/84) 1984 Construction.Q-listed material Audit determined that all shipped to jobsite was items met requirements.

not processed in accordance with Columbia's QA program.

(11/16 - 12/31/84) 1985 Construction Installation of seismic Open. Pending licensee gap seals and action.

penetrations,in Quality Class R and Important to safety systems did not meet BISCO Quality Program.

i l

Construction Deficiency Evaluation Reports (DER's) 10 CFR 50.55(e) 1.

8 DER NO.

DESCRIPTION CORRECTIVE MEASURES STATUS 78-1 Fabrication of Anchor Documentation reviewed Closed 04/11/78 Bolts for Major NSSS and corrected Not reportable components 78-2 Void in concrete place-Void repaired Closed 05/19/76 ment Not reportable 78-3 Stainless Steel pipe All pipe and pipe spools Final report spools from Youngstown Welding 11/17/78 j

and Engineering Company Reportable i

have been rejected, quar-l antined, and the company removed from the AVL by i

Pullman Power Products 78-4 Defective fillet welds Drawing corrected Closed 05/19/78 due to drafting error Not reportable on DWG's e

I i

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DER NO.

DESCRIPTION CORRECTIVE MEASURES STATUS 79-1 Voided 79-2 Weld sequence of Unit Weld sequence verified Final report di and Unit #2 polar correct 06/04/79 cran support girders Not reportable 79-3 Nath error in calcula-Calculation corrected Closed 06/01/79 tions Not reportable 79-4 Longitudinal weld de-NDE showed no defects Closed fects in S/S pipe Not reportable 79-5 Polar crane girder Procedures prepared and Closed 06/01/79 welds Implemented Not reportable 79-6 2" defective socket coating removed prior to closed 05/19/79 i

weld valves welding Not reportable 79-7 Polar crane bracket NDE showed satisfactory Closed 11/30/79 welds results Not reportable 79-8 Cracked Auxiliary Switches replaced; 100%

Closed 08/28/79 switches reinspection conducted Not reportable 79-9 Pipe spool heat treat-All material tested Closed 05/19/79 ment satisfactorily Not reportable 79-10 Safety-related pipe sup-A complete re-inspection Final report port assemblies in Unit program has been initi-03/06/80

  1. 1 sted with deficiencies Reportable being documented, training sessions updated, fillet weld gauges ^ supplied, and increased surveillance 79-12 Inadequate concrete Spe'cifications and pro-Final report strength achieved with cedures revised, all ac-12/30/80 pneumatically placed cessible areas chipped Reportable motor repairs and reworked, and all in-f accessible areas evaluated and dispositioned accept-as-is in NCR C-R2040 based on Design Criteria.

i J

DER NO.

DESCRIPTION

,,,,_ CORRECTIVE MEASURES ETATUS 79-13 Pump suction pipe con-A review of the various Final report fisaration on the high piping arrangements has 12/03/80 pressure safety injec-shown them to be accept-Not reportable tion pumps (EPSI) able under all existing guidelines and no further-action is required.

O l

t l

l

l DIR NO.

j DESCRIPTION CORRECT 192 MEASURES STATUS

'80-1 Inadequate design of Calculations performed; Closed 06/27/80 Seismic I instrument' verified satisfactory hot reportable supports 80-2 An error in calculations Calculations re-Closed 06/27/80 for tubing support performed Not reportable 80-3 Relating to undersized Accepted without repair. Final report structural steel fillet 12/24/80 welds Not reportable 80-4 Class 1E, 600V, Power Procedures revised; ap-Final report cable plicable cable repaired 11/05/80 Not reportable 80-5 Class 3, piping system All welds NDE'd satis-Final report welds factory 07/09/80 i

Not Reportable 80-6 Safety-related sway Stop work order notice Final report struts.

80-SW-3 closed and 07/10/81 NCR P-A-125 Not reportable revised to use-as-is.

80-7 Steam Generator piping Forms revised to show in-Final report welds' terpass temperature 07/03/80 Not reportable 80-8 Hilti drop-in anchors FCR written to delete Final report j

this type of anchor.

07/03/80 j

Not reportable j

80-9 operability failure of All installed and not in-Final report vertical fire dampers stalled fire dampers 09/15/80 found that did not meet Reportable the required tolerances were replaced. A re-design has been incorporated to elevate future problems.

80-10 Namco Controls Series Anchor / Darling to provide Final report

- EA180 limit switches replacement gaskets for 07/03/80 the subject valve limit Reportable switches.

80-11 Defective pressure switch MDA Scientific to pro-Final report in the chlorine de-vide alternate pressure 07/03/80 tectors switches after approval / Reportable qualification.

DER NO.

DESCR.1/ TION CORRECTIVE MEASUR$$

STATUS 80-12 Pipe spools with the Paper work corrected Final report l.

name 1.D. number 07/03/80 Not reportable 80-13 Dowel omission during Add dowels prior to con-Final report concrete placement crete placement which tie 07/08/80 into the slab.

Reportable 1

80-14 Pipe strap, pipe ear All installations veri-Final report full length welding fied correct 07/10/80 Not reportable 80-15 Closure of COMS1P, COMSIP to furnish modi-Final report incorporated contain-fication kit details and 07/09/80 ment gas analysis system instructions. Units to pump valve be modified with proper field change procedures 80-16 Inadequate embedment of A design change will be Final report anchor bolts for Units taplemented so that the 07/21/80 il and #2 seal tables seal table is adequately Reportable anchored in the reinforc-ed concrete and meets all seismic Category I require-ments.

80-17 Inadequate design of re-The design for all three Final report inforcing steel in the (3) units has been 07/21/80 walls of the Main Steam changed to add the re-Reportable Support Structure for quired amount of steel Unit il to meet established Design Criteria.

80-18 Blocked tendon sheaths Blockages removed and re-Final report in Unit il and #2 con-inspected 07/21/80 tainment Not reportable 80-19 Reinforcing steel shown Analysis performed; all Final report in the drawings may not stresses are within 11/06/80 be accurately reflected allowable limits Not reportable in the actual design in

' certain areas

]

80-20 Three (3) shipping studs Studs not needed; use-Final report jammed in reactor vessel as-is 07/30/80 Not reportable

l DER NO.

DESCRIPTION CORRECTIVE MEASURES STATUS l

1 l

80-21 Borg-Warner valves with Valves have been 1.D.'ed Final report stem extensions could and NCR'ed. Borg-Warner 07/29/80 loosen after a few will supply parts and in-Reportable cycles structions for rework 80-22 Dowel omission from con-lten was NCR'ed. Dis-Final report crete wall pour of Unit position was to drill 09/24/80 1

  1. 2 Control Building and grout the required Reportable i

'f dowels into wall I

80-23 Loose bushings'on corner Bechtel verified which Final report j

and IADA sway struts struts were in question- 03/02/81 through Corner & 1ADA.

Not reportable Bechtel will rework all identified struts using a C&L inspection and repair procedure 80-24 Excessive shear stresses The techtel calculations Final report in Unit il & #2 con-are being updated to be 03/30/81 crete slabs supporting consistent with the ac-Not reportable the safety injection tual data as submitted tanks 18, 2A, and 2B by combustion engineering 80-25 Improperly grouted Re-Voids repaired Final report actor Vessel Supports 10/17/80 Not reportable 80-26 Weld deficiencies on the None required Final report main control panel 07/14/81 Not reportable 80-27 Fractured bearing cap-Shims added; lugs ad-Closed 10/20/80 sules on Unit #1 con-justed tainment polar crane wheels i

80-28 Potential failure of All controllers were re-Final report temperature detection turned to McGraw-Edison 10/23/80 controllers used on for repair or replacement Reportable CT1-Nuclear Air Handling and Filtration equipment 80-29 Potential motor shaft Subject equipment is Final report breaksge in Six Eydrogen being reworked per sup-10/31/80 Monitors pliers recommendations Reportable

i DS NO.

DESCRIPTION CORRECTIVE MEASURES STATUS 80-30 Borg-Warner 3", 1500f, Use-as-is Final report motor operated gate submitted

. valve failure to close 11/05/82 under operating con-Not reportable ditions

)

80-31 Breakers in battery Raworked in accordance Final report chargers supplied by with suppliers recom-11/05/80 power conversion (EM-051) mendations Raportable t

80-32 Pipe cold spring for Training session closed 01/26/81 1

fit-up conducted Not reportable

{

80-33 Validity of Marathon SDDR supplied and closed 01/26/81 CMIR's for CF&1 steel Not reportable 80-34 Foxboro, Model 270, dis-SCN issued to track Closed 11/24/80 plays and housings re-equipment better Not reportable quire repair 80 Potential defect of Not used in safety-Closed 11/12/80 Rosemount Pressure related systems Not reportable transmitter on MS1V and MFIV 36 Loose bushings on ITI Bushing repaired Final report Grinnel sway struts 06/19/81 Not reportable l

80-37 Concrete void in Unit A procedure was develop-Final report

  1. 2 control Building Sump ed and implemented to 07/09/81 correct this deficiency Reportable 80-38 Pipe spools pulled to Bechtel removed and re-Final report facilitate installation installed new pipe to de- 01/12/81 of pipe supports may sign specs and retrain Reportable overstress welds associated personnel in erection of piping 80-39 Cable tray supports not Dwas have been revised, Final report meeting dwg. requirements cable trays inspected and 03/16/81

~~

reworked as needed Reportable 80-40 Control Building race-Drawing revised and Closed 12/11/80 ways and FSAR separation wiring relocated as Not reportable criteria necessary

7 4

DER NO.

DESCRIPTION CORRECTIVE MEASURES STATUS 80 Class 1E conductors Install additional sup-Final report coming within six ports or move termina-01/12/81 inches of non-class tion blocks or provide a Reportable 1E conductors on six ITE barrier satisfying Code Gould 480 volt load requirements for center isolation relay division between cabineta Class IE and Non-Class 1E wiring 80-42 Texas bolt material not Code Case N-310-1 Final report meeting ASME Section 111 accepted 01/27/82 Not reportable j

80-43 Field weld repair made Weld verified satis-Closed 02/06/81

(

on Borg-Warner valves factory Not reportable i

1 80-44 Missing screws from None required Closed 01/08/81 bottom of control cab-Not reportable inet instruments 80-45 Additional rebar rein-Reworked in accordance Final report forcement required by with engineering dis-02/04/81 drawing, not included in position (Isolated Case) Reportable containment placement i

80-46 ASME Section XI ultra-Indication considered Final report f

sonic pre-service ex-acceptable. Procedures 04/30/81 amination revealing in-revised accordingly.

Not reportable dications in Pullman power elbows 80-47 Deficiency in the con-Stiffner plates added to Final report i

tainment fuel trans-reduce stresses below 03/18/81 fer housing tube design allowable limits. Dwg's Reportable have been revised to in-1 corporate this change.

i

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l DER NO.

DESCRIPTION CORRICTIVE MEASURES STATUS 81-1 Concrete void in Unit 2 Repaired the void closed 02/09/81 Auxiliary Building Not reportable 81-2 Indications in radio-8" piping spool was Final report graphs of piping spools repaired 04/20/81 Not reportable j

81-3 GE fuse blocks may be None required Closed 03/12/81 loose / misaligned Not reportable 81-4 Corner and lada sway NCR invalidated DER cancelled struts 02/18/61 I

]

81-5 Swivel bearings on RCP None required Final report

]

cannot be rotated 06/12/61 i

Not reportable 81-4 Cracked turnbuckle Assemblies returned Final report i

assemblies for Control to manufacturer 04/15/81

(

Room lighting and replaced Reportable l

81-7 Auxiliary feedwater Hismatch corrected Closed 05/08/84 l

pump nozzle mismatch during fit-up Not reportable 81-8 Weld defects on caak Welds repaired per NCR Closed 04/29/81 loading Gate / Spent Not reportable l

Fuel Transfer Gate 81-9 Unacceptable radiograph Grinding mark repaired Closed 06/12/81 accepted and weld re-radiographer Not reportable 81-10 Hardened washers not Code case shall be docu-Final report used as required by mented 06/04/82 ASME Code Not reportable 81-11 Broken fiber on the Replace broken wire Final report armature of 4.36 KV 10/22/81 switchgear Not reportable 81-12 Mating force of 125VDC NCR dispositioned to Final report fuse blocks perform field modifi-11/02/82 cation (retaining clip)

Not reportable a

81-13 4.16KV switchgear Wiring errors corrected Final report wiring violates 09/18/81 separation criteria Reportable

)

l l

1 DER NO.

DESCRIPTION CORRECTIVE MEASURES STATUS i

81-14 A-354 anchor bolt fail-All accessible bolts Final report i

ures hardness tested. All 01/28/83

)

failures will be re-Repcrtable l

placed 1

81-15 Auxiliary feedwater SARCN to change 10 Final report q

pump may not deliver second requirement to 02/16/83 4

feedwater flow within 20, seconds Not reportable l

10 seconds 81-16 Operated GE breakers Bearing assemblies were Final report-may defora replaced 07/10/81 j

Reportable 81-17 Pipe supports fabri-Applicable drawing re-Final report cated without weld vised to show fillet 06/08/82 joint preparation weld only or increased Not reportable fillet veld 81-18 MCC's contain tie Re-tighten wire bundles Final report material which may un-12/30/81 revel or loosen Not reportable 81-19 Possible short circuit Repair necessary cir-Final report in Foxboro recorders cuits 08/03/81 Not reportable i

81-20 Weld details on pipe Hangers reworked; draw-Final report support drawing con-ings corrected 07/30/81 trary to ASME require-Reportable ments 81-21 Re-energization problem Power supplies and cir-Closed 07/13/81 in ESFAS relay cabinets cuit boards returned to Not reportable manufacturer 81-22 Premature time out of Replaced as required Final report AGASTAT relays during testing; appli-10/21/81, cable panel inspected Not reportable 81-23 MCC's have bent or Revised installation Closed 08/21/81

' broken terminal blocks instructions issued Not reportable j

i 81-24 Void in Unit il control Void repaired closed 08/19/81 1

Building concrete hot reportable 1

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DER NO.

DESCRIPTION CORREC'tIVE MEASURIS STATUS 81-25 AFW pumps could not be Storage procedures re-Final report rotated by hand vised-02/18/82 l

Not reportable 81-26

' Blocked tubes in Unit Felt pluge removed Final report il Steam Generators 11/18/81 Not reportable 81-27 Embed plate failed to None required closed 08/28/81 comply with weld cri-Not reportable i

teria J

81-28 Flexible conduit has Conduit replacea Closed 09/28/81 split jackets Not reportable 1

1 81-29 Failure of ASTM A490 Defective bolts replacec Final report bolts inspection prugram to 11/25/81, verify tension in high 05/11/83 strength bolts Reportable 81-30 Indication in ASME Code Indication removed; use-Final report i

pipe as-is 01/08/S2 Not reportable 81-31 Valve' operator material Affected valves modified Final report substitution 10/15/81 Reportable 81-32 EPS1 bearings and None Final report sleeves discolored 11/25/84 Not reportable

+

81-33 Sleeve bearir.g shifted Use-as-is

~

Closed 10/06/81 in upward direction Not reportable 81-34 Fillet welds on pipe Use-as-is closed 10/09/81 1

supports not thick Not reportable l

enough 81-35 Backfill erosion under Temporary gas, water Final report Unit #1 and #2 Auriliary lines removed; abandoned 05/20/82,

~

and Control buildings lines grouted 04/06/83 Reportable 81-36 Incorrect size fillet Support standards revised closed 10/05/61 weld on pipe support Not reportable

DER NO.

DESCRIPTION CORRECTIVE MEASURES STATUS l

81-37 Foxboro displays failed Displays modified to Final report environmental testing qualify environmentally 01/29/82 Not reportable 01-38 Minimum wall thickness calculations performed closed 10/20/81 violations to verify adequacy of Not reportable l

pipe 01-39 Gas Stripper has un-Pipe replaced; notifica-Final report documented section of tions to affected dis-02/28/83 pipe and welds ciplines Not reportable 81-40 Missing vertical dowels Dowels installed closed 11/20/81 in concrete poor in Not reportable Radwaste Building '

81-41 Possible attess in Unit Use-as-is Final report

  1. 2 containment piping 12/29/82 Not reportable 81-42 Unit #2 RCP bearing Crinding performed and Final report housing has sand holes holes sealed 01/29/82 Not reportable 81-43 Loose. nuts and couplings NCRs dispositioned to Final report on Units #1&#2 Steam correct deficiencies.

09/21/82, Generators inspection perforaed on 03/29/83 t' nit #3 Steam Generator 81-44 Pressure regulating Regulating valves re-Final report valves do not meet de-placed 07/06/82 sign requirements Not reportable 81-45 Unit 1 pressurizer Screws re-torqued and Final report missing lockwires lockwire installed 04/19/82 Not reportable i

81-46 Borg-Warner valve in-Valves modified as re-Final report stalled on horizontal quired 12/30/81 plane Reportable 81-47 -- Voids in Unit il MSSS Crout patch repaired Final report support floor slab 10/16/82 I

Not reportable 1

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DER NO.

DESCRIPTION CORRECTIVE MEASURES STATUS 81-48 Defective cylinder head Head replaced prior to Final report on Unit #2 DG start-up 01/05/82 Reportable 81-49 MSSS water level trans-Flex 1 hose re-installed Final report mitters may give er-to prevent erroneous 01/05/82, roneous readings output Reportable 81-50 Non-conservatism in de-SARCN to reflect correct closed 12/23/81 sign basis water con-design basis Not reportable sumption analysis 81-51 DG control cabinets Isolation and separation Final report wiring not sepsrated of wiring accomplished 08/23/84 per vendor documents Reportable 81-52 LPSI and CS pumps have Loose pins tack welded Final report loose anti-rotation pins 05/26/62 Not reportable 81-53 Wiring separation viola-Barriers erected to meet Final report tions in Main Control separation requirements 05/24/84 Reportable 81-54 Indication in Unit #1 Indication removed by Final report S/G #2 outlet nozzle grinding. NCR disposi-03/03/82 tioned. Use-as-is.

Not reportable 81-55 Water line leak under All temporary water, air Final report Auxiliary Building and gas lines removed.

09/29/84 51-56 Unit #1 letdown Heat Ez-The weld wa,s repaired Final report changers had improperly 04/05/82 welded stiffener rings Not reportable 81-57 Type HMA Auxiliary Re-NCR dispositioned rework Final report lays have excess unin-for affected leads 07/06/82 sulated leads l

s

. DER NO.

DESCRIpn0N CORRECTIVE MEASURES STATUS 82-1 Iz-core neutron monitor New cable purchased /re-Final report cables haveing greater placed which meets at-08/26/82 length and attenuation tenuation requirements Not reportable than design 82-2 During an internal in-Dispositioned " Rework" Final report spection (of heat ex-and since accepted by 03/22/84 changers), 4 welds were radiographic examination Not reportable found visually unaccept-able 82-3 Diesel generators lube Repiscenent of defective Final report oil strainer baskets re-baskets 03/23/82 quire replacements per Reportable 10CFR21 by Cooper Energy Services 82-4 Design specification All installed clamps cor-Final report drawings for instrument rected to comply with the 07/23/84 tubing clamps do not Code Reportable show locknuts as re-guired by ASME Code 82-5 Unit #2 reactor coolant NCR dispositioned to re-Final report pump. delivered with sand move the blasting sand 06/16/82 in cooler chamber housing Not reportable 82 Unit #3 valves (11 Qualification documenta-Final report total) shipped and re-tion processed. NCR is- 02/18/82 moved from receiving sued against the Unit #3 Not reportable area without qualifica-equipment as required i

tion documentation 82-7 Five Star Special "150" WPp/QC1 revised to review Final report grout used in contain-manufacturer's final cer- 04/07/82 ment construction ob-tification. Remove Five Not reportable served stratification Star Special "150" grout from approved list 82-8 G.E. switchgear has NCRs dispositioned to Final report parts not certified by replace the identified 10/25/82 subsuppliers for nuclear components correcting all Not reportable use equipment deliveries to the jobsite

DER NO.

DESCRIPTION CORRECTIVE ME/.$URF.S _

STATUS 82-9 Thernowells in diesel NCRs dispositioned L.

Final report generator lube oil sys-replace thernovells 11/04/82 tems by Cooper Energy Not reportable l

were not procured to Code 82-10 Code material 1.D. nos.

Addenda incorporated as Final report obliterated on 8 pipe applicable 04/27/82 supports in Unit #2 Not reportable containment and MSSS due to galvanizing 82-11 Six nozzles in the re-NCR dispositioned to r.1-Final report actor bottom head had low tube installation 03/15/82 terosity in the weld work to proceed Not reportable sone, deep surface de-fects, and nicked welding surfaces 82-?.2 Instrrrtut clamps in-NCR dispositioned to Final report stall 24 without calcula-review / rework all dis-06/08/82 tions for thermal ex-crepancies of installa-Reportable pansion tion 82-13 Reinforcing bars omitted Borizontal rebars in-Final report from Unit #3 fuel trans-atalled 06/04/82 fer tube inspection Not reportable station 82-14 Units il and #2 instru-Fasteners replaced with Final report ment installation bolting certified fasteners 07/07/82 procured to ASME 111 Reportable Code was used without issue control 82-15 ASME 111 Code pipe sup-NCRs dispositioned to Final report l

ports not traceable to check and verify each 07/14/82 QIB material material drawn from Reportable storage for installation 82-16.: Condent. ate pots were NCR dispositioned use-as-Closed 04/16/82 found to be concon-is Not reportable forming m

~ - - ' - -

DER NO.

DESCRIPTION CORRECTIVE MEASURES STATUS 1

82-17 Sechtel supplier docw-The computerized SDR has Final report ment register errors may been corrected, preclud-12/09/82 allow outdated CE pro-ing redundant logging Wot reportable cedures to be used for Unit #1 instrument calibration 82-18 Pump motors have metal NCR'dispositioned to Final report particles in lube oil flush and replace the 09/16/82 and deterioration of motor oil Not reportable internal epoxy coating 82-19 Class IE MCC's burned NCRs dispositioned to Final report out due to damage during replace damaged com-09/14/82 testing ponents Not reportable 82-20 20' section of 8" sched-NCR dispositioned use-Closed 05/05/82 ule 80 pipe has numerous as-is for the installed Not reportable areas below minimum wall section. The non-in-thickness stalled sectiou returned to manufacturer 82-21 Cable support structure NCR dispositioned to Closed 05/06/82 i

had shop welds not in use-as-is since no rework Not reportable i

accordance with drawing required 82-22 Knee-braced steel NCR dispositioned use-as-Closed 06/03/82 framing of the MSSS in-is since no rework re-Not reportable correctly quired 82-23 Inspection revealed Piping spool repaired.

Closed 05/14/82 numerous unauthorized Wall thickness verifiec Not reportable grinding on $1 system 82-24 Weld procedure not pre-Dispositioned use-as-is Final report qualified by Ametek-09/15/82 Straza for reactor bot Not reportable leg pipe stops 82-25 Q-Class pipe in auxiliary " Cracks" were actually Closed 06/11/82

_ building has visible shallow surface, proving Not reportable 2"-4" indications near adequate wall thickness weld 82-26 Hounting failures of Broken brackets revelded. Final report valve position in-Other similar switches 09/09/82 dicating switches inspected Not report &ble

l

-4 DER NO.

DESCRIPTION CORRECTIVE MEASURE 3' STATUS Returned to supplier for closed 06/01/82 82-27 Fuel building gate Not reportable supports improperly rework welded 82-28

' Joy fan blade locknuts NCR dispositioned use-Final report 07/23/82 under-torqued as-is f

Not reportable 82-29 Multiple libear in-NCRs dispositioned use-Final report 11/24/82 dication on Main as-is Not reportable Feedwater lines 1

82-30 Cleanliness control not VGS inspected and Final report maintained on Unit #1 cleaned 07/20/82 Not reportable VGS 82-31 Wiring error in the Correct wiring error Closed 06/24/82 Not reportable Plant Monitoring System 82-32 Purge das material in Material removed and Closed 07/02/82 check valve reassembled Not reportable CH system 82-33 leakage past 3" Anchor-Set screw staked in Final report 08/20/82 Darling check valve place Not reportable I

82-34 Concrete void in Unit Repair the void Final report 07/23/82 il MSSS Not reportable 82-35 Unit #2 LPSI and CS Field personnel in-Final report I

pump hold down bolts structed on verification 09/29/82 under-torqued of torque valves Not reportable 82-36 DG Control Panel wiring New lugs installed Final report 08/06/82 not crisped Reportable Procedures rewritten for Final report 82-37 Class II viring in-maintenance program hy-11/15/82, properly crimped draulic crisp units. All 07/18/82 future crimps to be done Reportable

~

at a minimum of 7900 psi l

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DER NO.

DESCRIPTION CORRECTIVE MEASURES STATUS 82-38 Containment isolation Bolts retightened Final report valves had actuator 01/12/83 bolts loose Not reportable 82-39 Valve limit switches All switches inspected Final report below flood level in and found satisfactory 05/16/83 containment Not reportable i

l 82-40 Unit #1 circuit breakers TesIproceduresre-Final report incorrectly set after written; testing pro-12/28/82 testing gram revised Reportable 82-41 Improperly crisped lugs New connections in-Final report in Unit #3 switchgear stalled as applicable 11/23/82 Reportable 82-42 Unit #1 RCP nozzle weld Stainless steel portion Final report leak of nozzel replaced by a 03/28/83 double piece of incenel Reportable 82-43 laproperly crisped lugs All lugs inspected and Final report in Unit #2 repaired as necessary 02/07/83 Reportable 82-44 Borg-Warner valve Motor operators re-Final report operators not qualified placed with qualified 11/15/82 for use in containment operators Reportable 82-46 ITT-Barton transmitters Transmitters replaced Final report do not meet requirements with Rosemount; SARCN to 03/15/84 change diversity re-Reportable quirements' 82-47 Minimum wall thickness inspect and repair the Final report violations on 24" pipe areas of corrosion 11/19/82 Reportable 82-48 Check valves siezed open Check valves redesigned; Final report by welding haat all check valves flow 12/07/82 tested Reportable c

82-49

- Unit il and #2 S/G has Repisce beam attachments Final report pipe support incorrectly with applicable brackets 10/08/82 welded Reportable

I DER NO.

DESCR1pTION CORRECTIVE MEASURES STATUS 4

82-50' Flexible conduit coup-Conduits modified for Final report lings may be damsged proper support 03/09/84 during seismic event Reportable 82-51 Pipe line failure in Plasite repairs effected Final report Unit #1 essential for applicable piping 01/09/84 l

cooling system Reportable 82-52 Pipe supports incor-Inspections of Unit il Final report rectly installed pipe supports 11/08/82 Not reportable 82-53 Joy fan blade failure Containment lines plate Final report in Unit il repaired; fan blade re-08/29/83 placed; all fans rein-Not reportable spected 82-54 MSIV's have internal Valves reinspected and Final report corrosion refurbished 01/26/83 Reportable 82-55 DC motor feeder cables Undersized cable re-Final report may not provide suf-placed; cable sizing 02/23/83 ficient orarating volt-procedure revised Reportable age 82-56 Condensate storage tank Calculations performed Final report scaled down without new on tank; satisfactory as 07/21/83 seismic calculations built Not reportable 82-57 Auxiliary feedwater Valves replaced with Final report valves are carbon steel stainless steel bodies 12/28/82 instead of stainless Reportable steel 82-58 DG cubicles may not be DCP issued to anchor Final report qualified seismically cubicles acceptably 11/22/82 Reportable 82-59 DG crankcase sump coat-Isose paint removed from Final report l

_, ing flakuza off sump 11/22/82 l

Not reportable l

G2-40 DG has non-conforming Defective piston re-Final report material certification placed 11/22/82 Reportable L_____-____---

I 4

DER NO.

DESCRIPTION CORR 1,CTIVE MEASURES STATUS 82-61

.RCP diffuser ring cap Cap screw material Final report screws may fail changed; wedging device 01/25/84 added Not reportable 82-62 ESFAS DC power supply Review conducted to Final report ground detectors failed assure consistency be-08/03/83 testing tween test procedures Not reportable and specifications 82-63 Calculation error in Design analysis showed Final report seismic calculation of acceptable as-built 06/27/83 RWI condition Not reportable 82-64 Dissimilar metal socket Welds replaced with cor-Final report welds rect material 11/29/82 Not reportable 82-65 Battery racks may not Additional calculations closed 11/04/82 be seismically quali-performed. Racks to be Not reportable fied replaced as necessary 82-66 Demineralized water Water removed Closed 11/10/82 leaked into the reactor Not reportable vessel 82-67 ISFAS power supplies do Power supplies replaced Final report not meet specifications 12/16/82 Not reportable 82-68 Cables to startup trans-Use-as-is Final report formers may not carry 09/16/83 I

full current Not reportable 1

82-69 Incorrectly marked fuses Replaced fuses Final report in CEDM's 03/08/83 Not reportable 82-70 Improper grinding next Use-as-is closed 11/18/82 to weld Not reportable 82-71 Loose bolt holding yoke Re-torqued the bolt Final report

' to valve body 01/26/83 Not reportable 82-72 Concrete void in Unit Grouting program ini-Final report

  1. 2 containment wall tiated to fill voids 06/30/83 Reportable

DER NO.

DESCRIPTION CORRECTIVE MEASURES STATUS 82-73 Pipe support clamps in Defective clamps re-Final report Unit #2 MSSS may have placed; inspection con-01/31/84 excess gap ducted to identify other Raportable deficiencies 82-74 Adjustable resistors Modification effected to Final report have nong size bolts replace nuts and washers 12/23/82 Not reportable 82-75 Refueling water tank leproper studs, clips Final report suction strainers in-replaced 12/23/82 properly secured Reportable 82-76 Target rock valves do Solenoid operators modi-Final report not meet specification /

fied; replace target 07/11/84 test requirements rock solenoids with Reportable valcor 82-77 Foxboro displays failed Qualified models supplied Final report Class 1E testing for use 12/23/82 Not reportable 82-78 Improperly crimped lugs All lugs inspected;.de-Final report in water chiller control fective lugs replaced 01/17/83 panels Reportable 82-79 Control air tubing Tubing separated to meet Final report violates separation requirements 01/17/83 criteria Not reportable 82-60 Iow insulation valves Terminal blocks replaced Final report for terminals blocks with splices 08/31/64 Not reportable 82-81 R-Class instruments Honeywell instruments Final report used in lieu of Q-Class inspected for conform-04/12/83 in DG control cabinets ance Reportable 82-82 Hechanical spubbers do WCRs dispositioned to Final report not permit 5 nove-rework the affected 01/19/83 ment without binding snubbers Reportable 82-83 DG butterfly valves did Valves interchanged and closed 01/06/83 not comply with require-replaced Not reportable ments i

i 1

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pER NO.

DESCRIPTION CORRECTIVE MEASURES STATUS 82-84 Class 1E load centers in Space heaters inspected Final report Unit il had internals for correct voltage 04/19/83 j

damage by space heaters Not reportable 82-85 Earlo relay panels in Incorrect relays re-Final report Unit #1 failed testing placed with qualified 03/07/83 relays Reportable l

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DER NO.

DESCRIPTION CORRECTIVE MEASURES STATUS 83-1 DG voltage regulating Transformers repaired per Final report system may not perform DCP 02/16/83 as specified Reportable 83-2 Valve operators inter-Affected operators were Final report I

changed replaced 05/03/84 l

Reportable 83-3 Foreign material in Housing flushed and Final report bearing housing of cleaned 02/28/84 Unit 1 HPSI pump Not reportable 83-4 Test procedures for air Procedures revised; Final report handling units do not retests performed 04/27/84 meet t.NSI 510 Not reportable 83-5 Weld undercut on pipe Use as is Final report in SI system 02/28/83 Not reportable 83 4 Undersize shock sup-Shock suppressor replaced Final report presor in Unit 1 02/28/83 Containment Reportable 83-7 Maxi-bolt anchors Replaced affected bolts Final report improperly installed 03/04/83 Not reportable 83-8 Hydrogen recombiner Existing timers replaced Final report failed Qualification 02/28/83 test Reportable 83-9 Unit 1 LPS1 pumps Both LPSI trains flushed Final report strainers and cleaned 09/06/83 Not reportable 83-10 Main steam relief valves Valves returned to manu-Final report exceed 5% blowdown facturer for refurbish-02/28/84 unit ment Not reportable 83-11

. Exide batteries may Stress or batteries Final report

~ leak or corrode at relieved; permanent 06/14/83 terminals repairs effected Not reportable 83-1.2 480V MCC interlocks may Interlocks changed Final report malfunction out under GE supervision 05/03/83 Reportable

L DER NO.

DESCRIPTION CORRECTIVE MEASURES STATUS 1

83-13 Violation of Tagout Training conducted on Final report requirements tagging procedures 07/14/83 Not reportable 83-14 14aking capacitors Defective relays replaced Final report l

in DG relays 09/27/83 Reportable

^

83-15 A 354 Anchor bolt bone Torque valve determin-Final report under installation torque ation methodology 09/23/83 changed; drawings Reportable revised 83-16 DG govenor and voltage DCP issued to correct Final report regulator do not reset deficiency 05/03/83 after trip Reportable 83-17 Fire protection switches All damaged switches Final report failed to meet TMI replaced 07/19/83 criteria Reportable 83-18 Pipe supports do not Additional hex nuts Final report meet Seismic IX require-installed; drawing 04/28/83 ments revised Not reportable 83-19 Shock arrestors do not Applicable shock Final report function properly arrestors replaced 01/03/84 Not reportable 83-20 startup test personnel All personnel properly Final report qualification trained and. qualified 04/29/83 Not reportable 83-21 LPS1 pump operated in Training provided to Final report violation of procedures operators 05/06/83 Not reportable 83-22 Nydrogen recombiner Circuit breakers Final report circuit breaker failed replaced 10/24/83 to operate improperly Reportable 83-23

- MS1V bypass isolation Solenoid valves replaced Closed valves failed to close 05/10/83 within 5 seconds Not reportable 83-24 DG lube oil and jacket New heaters installed Final report water heaters do not 05/18/83 maintain temperatures Reportable

-DER NO.

DESCRIPTION CORRECTIVE MEASURES STATUS l

l 83-25 Instrument tubing does Use-as-is; revised Final report

]

l act have boundary class specifications issued 09/21/83 i

break Not reportable l

83-26 BOP ESFAS module,s failed Cabinets modified to Final report I

testing due to over-increase ventilation; 10/28/83 beating drawings revised Not reportable 83-27 Need position indication Adjust switches s's closed switches functioning necessary; O-ring 04/28/83 improperly and terminal boards Notreportable replaced 83-28 Snubbers installed in Use as is; Specification Final report violation of reserve change to clarify pro-06/08/83 range requirements cedure Not reportable 83-29 Nangers in SI system Supports repaired; draw-Final report installed incorrectly ings revised 06/06/83 Reportable 83-30 A354 bolt broke while Torque procedures Final report torquing on Unit 2 AFW revised; drawings 01/30/84 pump revised Not reportable 83-31 Temperature rise in DG Ventilation modifications Final report control cabinet could made to provide forced 08/23/83 exceed design ventilation Reportable 83-32 Socket welds in Unit 1 Transition pieces instal-Final report S/G 1ed; drawings revised 02/29/84 Not reportable 83-33 GE breakers with EC-1 Defects corrected per Final report trips nay have defect NCR dispositioned 06/24/83 Reportable 83-34 Instrument racks in Defective welds repaired Final report Unit 2 have surface 09/19/83 cracks Not reportable

~~

83-35 Inverters produced Eigh frequency snubber Final report voltage spikes on DC capacitor reworked 01/09/84 supply bus Reportable 83-36 Excessive cycling of Actuators refurbished Final report bydramotor actuators and retested; Training 12/21/83 program conducted Not reportable

DER NO.

DESCRIPTION CORRECTIVE MEASURES STATUS 83-37 Missed factory operations Defects repaired as Final report on Unit 3 S/G' appropriate 12/05/84 Reportable 83-38 Clip angles used for HVAC Use-ae-is Final report l

supports do not meet 10/06/83 l

requirements Not reportable 83-39 Rejectable indications Reworked pump case;.

Final report on Unit 1 RCP inspected an other welds 01/03/64 Not reportable 83-40 Unit 1 LPSI and CS pump New lower end brackets Final report motors leaking oil instaHed; new design 02/02/84 housing Reportable 83-41 Flooding in Control Circulating water intake Final report l

Building canal sealed; electrical 09/21/83 ducts sealed; a u joints Reportable sealed 83-42 Failed thernoven s Original thernowens Final report in the RCS replaced with new, 09/14/84-redesigned thernowens Reportable 83-43 Improper crisp termina-All relay cabinets by Final report tions Harlo reinspected; dis-09/27/84 crepancies will be Reportable corrected 83-44 Wiring errors in PPS Wiring corrected sind Final report cabinets retested 08/15/83 Reportable 83-45 Cable separations in Wiring redone in accor-Final report Unit 1 Control Roon dance with applicable 09/26/83 panels requirements; procedures Reportable revised 83-46 Value overtorqued during Adjusted alectrical Final report

.. hydrostatic testing leads and reed switch 01/09/84 Reportable 83-47 Power supplies may damage Additional fuses in-F! sal report instrument conductor stau ed 10/17/83 penetrations Reportable

--________-.--__m___._m-

DER NO.

DESCRIPTION CORRECTIVE MEASURES STATUS 83-48

. Solenoid valves Refurbished with high Final report subjected to excessive temperature connectors, 10/28/83 Not heat-lead wires and 0-rings reportable 83-49 Broken impeller blades / Diffuser redesigned; Final report diffuser bolts capscrew numbers 09/14/84 Not increased; impellers reportable backfilled;' bearing sleeves replaced 83-50 Combined with DER 83-49 83-51 AFW pump failed testing Surveillance test path Final report eliminated; SARCN to 09/25/84 change required flow Reportable rates 83-52 Power supplies feed Filter elements Final report noise into 125 VDC bus installed; annunciators 12/22/83 returned for re-work Reportable 85-53 Unit 3 embed plates do Replace defective plates Final report not meet specification plug weld anchor bolts 10/15/84 Reportable 83-54 Washers found in Unit 1 Loose parts removed; Final report S/G's remainder of system 01/17/84 Not inspected reportable 83-55 Thermal liner on cold Liners removed from Final report leg of RCP 1A sissing system 12/30/84 Not reportable 83-56 Discrepancies with Larger hydraulic Final report MSIV's reservoir; pump material 04/13/84 replaced; relief valve Reportable installed l

83-57 Cracks in CEA shroud 4 and 12 finger guides Final report j

removed; enubbers added 09/14/84 j

for lateral support Reportable j

83-63 HPSI isolation. valves Readjusted limit Final report failed to open switches tack welded 10/9/84 yokes to bonnet Reportable 83-64 Pressure relief valves Test rig replaced Final report failed testing 05/24/84 Not l

reportable 1

l

4 DER NO.

DESCRIPTION CORRECTIVE MEASURES STATUS 83-65 Safety relief valves-Valves reconditioned and Final report found dirty and rusted tested; cleanliness 01/23/84 requirements' addressed Reportabic 83-66 AFW pump impeller wear Wear ring material Final report

. ring fractured changed; sent to 06/21/84 manufacturer for rework Reportable 83-67 Ex-core detectors below Detectors relocated Final report flood level above flood level 01/23/84 Reportable 4

83-68 Battery racks Non-conforming hardware Final report

]

constructed with replaced 02/09/84 materials not meeting Reportable specifications 83-69 Seismic supports on Added additional shaft Final report Posi-Seal valves supports to raise 07/11/84 incorrectly installed frequency, validating Reportable

.l seismic analysic j

83-70

. Wiring in ERT Cabinets Wiring rerouted; metix Final report not in conformance with barriers installed; 02/28/84 specification color coding of wiring Reportable 83-71 Shock arrestors may have Snubbers replaced as Final report generic defect required 04/24/84 Reportable 83-72 Undersize velds in Specification revised; Final report Unit 1 Auxiliary Training for QC 03/14/84 i

Building inspectors Not reportable 83-73 Unqualified power Replaced with safety Final report supplies installed IE grade power supplies 12/6/84 instrument cabinets improved procedures, Reportable retrained personnel 83-74 Undersize welds in Inspections conducted on Final report Unit 1 Auxiliary all units pipe supports 09/21/84 Building for weld size Not reportable 83-75 Improperly torqued bolts Bolts retorqued Final report on panel filler assemblies 07/24/84 L

Not reportable l

83-76 Improper AFW pump logic Logic diagram revised; Final report l

modifications on 05/07/84 l

existing logic Reportable 83-77 Unit 2 concrete pour Honeycombed areas Final report contains honeycombs repaired 07/13/84 Not reportable l

l i

I 4

t

.s DER NO.

DESCRIPTION CORRECTIVE MEASURES STATUS

{

84-)

Methodology used to Procedures revised to Final report track required retesting provide a documented submitted-04/09/84 activities program to track Not reportabic requirements for

]

outstanding preoperational 1

I retest after work is performed on a previously tested structure system or component 84-2 Rust, scale, and pitting NCRs were dispositioned Final report in the clevis and arm of use-as-is 07/13/84 Not several 51 and CH valves reportable 84-3 Feedwater isolation Inspect and rework FW1Vs Final report valves; lower 4-way and MSIVs to remove 05/25/84 valve found stuck during unacceptable pipe Reportable testing.

sealant and replace with Loctite No. 277 prior to fuel load 84-4 External security wiring Contains proprietary Closed 01/27/84 not in conformance with security information per Not reportable specification 10 CFR 2.790 84-5 D'ebris found in reactor NCR dispositioned to Closed 02/10/84 internal during movement clean area and return Not reportable of the CEA Shroud tools to proper storage Assembly from the UGS 84-6 Possible deficiencies in Replaced deficient Final report absolute and deviation potentiometers 12/12/84 alarm modules Reportable 84-7 Failure te provide NCRs initiated to Final report corrective action as reinstate rework on 07/13/84 stated in DER 80-21 valves requiring Reportable modifications 84-8 ITT/Barton Model 763 Transmitters will be Final report Transmitters do not meet replaced or refurbished 07/24/84 specifications Reportable 84-9 Relating to CAD welding Welding procedure Spec. Final Report for cathodic protection Qualified to ASME 10/15/84 ground connection Section III Not reportable 84-10 Abnormal number of 100% inspection revealed Final report single element RTDs no problem with the RTDs 08/01/84 Not open-circuited reportable

DER NO.

DESCRIPTION CORRECTIVE MEASURES STATUS 84-12 Zone 111 violations of The entire Unit 1 RCS Final report RCP 1A and S/G #1 returned to Class B 09/10/84 cleanliness, and the Not reportable demonstration test completed 84-13 Relating to HVAC Completed walkdowns.

Final report acceptance criteria Correct where required. 4/29/85 Rouse drawings Reportable 84-14 Some studs and nuts DCN issued to allow the Closed 03/13/84 installed on SI & RC use of SA-194, GR BM Not reportable systems which do not material in the boric meet ASME requirements acid related systems, as for boric acid service applicable 84-15 Relating to welds Under evaluation.

Final report attaching pipe restraint Revised inspection 11/15/84 Not supports less than criteria. Corrected reportable j

design-calculated deficiencies where dimensions in Unit 2 required.

84-16 ESFAS relay cabinets Added stiffener plates Final report baseplates to cabinets and updated 08/02/84 installation DWC's Reportable i

84-17 The core shroud envelope Measurements of core Closed 04/23/84 shroud panels Not reportable accomplished as required 84-18 Wiring error on LPSI Wiring errors on control Final report pump "B" CS-3 switch switch corrected 09/10/84 Not reportable 84-19 Improperly installed Nonconforming flanges Final report blind flanges removed and replaced to 07/30/84 Not meet Piping Material reportable Classifications 84-20 Displacement of a Proper operation of SI Final report connecting line in the valve was verified 10/15/84 Not SI system reportable 84-21 Rosemount transmitters Replaced mounting Final report not torqued to specified hardware.

Issuance of 12/8/84 valve specific instructions.

Reportable Review of Q-clasc deficiencies.

)

i 1

_-.-__________.____.___________U

"h DER NO.

DESCRIPTION CORRECTIVE MEASURES STATUS 84-22 Unit #1 CEA shroud Contaminated area Final report L

. support contaminated; cleaned and. checked for 08/01/84

-with oil

' corrosion..011 Reportable retention bars are being added to the Polar Cranes to contain oil in gear Case.

84-23 Auxiliary feedwater pump No future reflow cire.

Final report "B" discharge valve to testing will be done.

07/12/84 condensate storage tank Recire, valves V018 and Reportable V027 will be replaced by spectacle flanges.

84-24 Limitorque valve Retorqued valves in Final Report operators loose on valve question sampled 10/23/84 bodies additional valves Reportable clarification of instructions retraining personnel 84-25 Containment supply Vendor ensured proper Final Report registers would not hardware in the future.

11/27/84 cycle Modification of Reportable registers.

84-26 Improperly tested or Interlocks will be Final report adjusted interlock manually tested unless 09/21/84 properly tested Reportable personnel are performing the function 84-27 Improperly handled Reinspection and Final Report instrumentation from correction of 12/12/84-Waldinger Corp.

deficiencies. Review of Reportable procedures. Retraining.

84-28 Diesel generator fuel Modification of attached Final report lines pipe 2/15/85 Not reportable 84-29 Build up of material on Clean, recoat with Final report Unit #2 diesel generator plasito lining 09/25/84 Reportable EX 84-30 Improper documentation Review of all code-Final report of diesel generator related documentation 09/18/84 concluded correct and on Not reportable components file; use-as-is 84-32 Superceded by DER 84-34

i DER NO.

DESCRIPTION CORRECTIVE MEASURES STATUS 84-33 Incorrectly installed Weld added Final report hanger support assembly 09/21/34 Not reportable 84-34 Critical friction type Reworked / repaired keyway Final report high strength connectors bolts. Revision of 10/26/84 drawings. Training of Reportable personnel.

84-35 Setpoint potentiometers Potentiometers replaced Final report in the PPS drift outside 09/18/84 Not of tolerance reportable 84-36 SI valve stalls just of f Replacement of Final report closing seat when applicable valves.

11/28/84 i

opening or closing Inspected downstream Reportable piping.

84-37 Unauthorized / unqualified Identification and Final report duct sealant qualification of 12/7/85 sealants. Retrained Reportable personnel.

84-38 Improperly welded flange Rework / repair by adding Final report in Unit #2 filler material 09/18/84 Reportable 84-39 LPSI and containment Use-as-is, but do not Final report spray pumps have run pump in the 2500 to 09/26/84 Not

]

experienced abnormal 3500 flow range during reportable i

rumbling noises shutdown cooling mode of operation 84-40 Unit #2 auxiliary Improved chemistry.

Final report feedwater pump has Replacement of 12/14/84 Not corrosion applicable parts.

reportable 84-41 Adequacy of Cardinal Personnel training.

Final report Industrial Products Revised audit procedures.12/13/84 Not program for supplier Revised inspection reportable qualification procedures.

Instituted user tests.

84-42 Unqualified torque Addressed in DER 83-73 Final report switches installed on 10/30/84 Not safety related valves reportable 84-43 HPSI 3" gate valve Valve stem cleaned and Closed 07/18/84 failure to open lubricated Not reportable

h

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L p

-DER NO.

DESCRIPTION CORRECTIVE MEASURES-STATUS l

L 84-44

. Fatigue failures of the. Implementation of a Final report l

charging pumps

maintenance and-11/28/84 Not

(

inspection program -

reportable 84-45.

2 Relating to spot welding Retested stud welds Final report-on skid mounting 10/19/84 Not indication and control reportable 84-46 Refueling water tank DCPs prepared to perform Final. report penetration sleeves; required grouting work 09/24/84 e

f connection would be Reportable overstressed during a seismic event t

84-47 Hacksaw blade in the Weld on line SI 130 was closed 07/24/84

-Unit #3 SI system completed Not reportable 84-48 Improper material for Replaced expansion plugs Final report:

piep. plugs on MSIV 10/18/84 Reportable 84-49; Auxiliary feedwater Mini-flow individually Final report' system experiences adjusted for each pump 09/26/84

~

hydraulic' resonance to reduce the vibration Reportable 84-50 Main steam isolation:

Reivsed Na PT curves.

Final Report valves-do not close as Changed alarm setpoint.

10/25/84 required Reduced prechange Reportable pressure. Increased accumulator operating pressure.

84-51 Failure of turbine-Changes initiated to Final report driven auxiliary reflect the feedwater 09/26/84 feedwater pump to quick delivery time change Reportable start from ambient from 20 to 30 seconds j

conditions 84-52 Relating to the DCPs initiated to Final report atmospheric dump valve; increase the thickness 09/26/84 Not a review of the seismic of the resistor base reportable analysis report flange to two inches determined that the base flange of the resistor is overstressed during an SSE and will break j

84-53 Nuts on bolts found Reworked valves.

Final report

]

loose on PC and CH Revised procedures.

12/28/84 Not valves Retrained personnel.

reportable

DER NO.

DESCRIPTION CORRECTIVE MEASURES STATUS 84-54 Containment sump E.ework of valve Final-report isolation valve operators 12/12/84 Reportable 84 'Non "Q" naterial Replacement of non-Class Final-report installed ~in QlE modules with Class 12/6/84 instrumentation cabinets modules. Revised Reportable procedures.

84-56'-

Fire dampers were found Modified and reworked Final report to close inconsistently dampers 12/8/84 i

L Reportable 84-57 Evaluation relating to SARCN to change time Closed 09/19/84-radioactive waste drain from 10 seconds to 40 Not reportable system seconds 84-58 Auxiliary feedwater Cleaning or replacement Final. report system solenoid valve of affected valves 11/12/84 Not failed to open in reportable response to AFAS signal 84-59 MCC cables damaged by Replaced damaged cable.

Final Report fire stops Installed metal edge-10/9/84 protectors.

Reportable.

84-60 Improper lubricant used Affected valve operators-Final eport in Limitorque valve flushed and relubricated.11/12/84 operators Reportable 84-61 Auxiliary pressurizer Under evaluation.

Final report spray system-loop valve Installation lof failed-10/7/84 Not potential to stop open close isolation valve.

reportable 84-62 Load sequencer did not Various hardware and Final report function properly during circuitry modifications.12/8/84 Not safeguards testing reportable 84-63 SIT vent valve would not Cleaning or replacement Final report close during testing of affected valves 11/12/84 Not reportable 84-64 Snubbers will not cycle Replacement or upgrading Final report 1

of snubbers.

12/12/84 Installation of low Reportable friction slide plates.

l 84-65 Inst. leads removed from Leads removed from Core Final report UGS have shown splitting Support Barrel 11/12/84 Not of outer sheath reportable

DER NO.

DESCRIPTION

-CORRECTIVE MEASURES STATUS 84-66 Downcomer f eedwater Modifications to Final report isolation valves actuators.

10/3/84 Reportable 84-67 Steam generator system C1 caning or replacement Final report valve solenoid of affected valves 11/12/84 Not operations at low voltage reportable i

84-68 ESC "A" would not Installation of new Final report resequence due to temperature switches.

11/15/85 temperature switch trip Modification to timers Reportable after LOP I

84-69 Reactor protection Removal of barrier Final report system shunt trip material from relays 11/9/84 Not reportable contacts 84-70 Diesel engine "A" in Lubricate control Closed 09/28/84 Unit #1 tripped off mechanism Not reportable because of engine overspeed 84-71 A spurious load shed of None required Closed 09/17/84 the 4160 V SWGR SO4 Not reportable Feeder Breaker 84-72 During pre-op test S1 Modifications of HPSI Final report valve torqued.out near valves 12/12/84 the closed seat Reportable 84-73 Test cards for excore Replaced and modified Final report system have an incorrect test cards.

11/5/84 value for "R26" Reportable 84-74 Inverters failed pre-op Replacement of Final report testing components. Procedure 12/14/84 Not revisiens.

reportable 84-75 DG essential exhaust fan Not reportable fafis to start within 5 seconds in Mode 1 or 4 operation 84-76 STAT or temps could be Modifications to air Final report exceeded supply and exhaust 12/12/84 Not openings.

reportable 84-77 Rosemount transmitters Replacement /

Final report manufactured after refurbishment of 12/6/84 January 10, 1984 may not defective transmitters. Reportable have hermetic seal.

t -

'S y

l DER NO.

DESCRIPTION CORRECTIVE MEASURES STATUS 84-78 Valcor valves experience Installation of dropping Final report coil failures resistors 11/16/84 Reportable 84-79 Broken terminal lug on Not reportable DG could cause abnormal temperature rise 84-80 DG "A" tripped of f on Not reportable overspeed when load was removed 84-81 65%-90% hesitation of Modifications of HPSI Final report the open position when valves 12/12/84 3 of.4 valves are in Reportable closed position 84-82 Improper mate between Final report seat and disc of Si check 11/9/84 Not valve reportable 84-83 HPS1 "A" injection lines Modify design of HPSI Final report experiencing cavitation injection lines 11/25/84 Not reportable 84-84 D'iscrepancy between Final report CESSAR Section 5.1.4 and 10/26/84 Not CESSAR Chapter 15, dealing reportable with valve closure time 84-85 Containment purge valve Final report closing time on 10/26/84 Not Containment Isolation reportable Activation Signal assumed in CESSAR 15-4-8 Amend 6 or later was not assumed in Palo Verde FSAR 84-88 Grout Missing Under Placement of grout under Final report Downcomer Feedwater feedwater lines 11/30/84 Lines Reportable 84-89 Barton Transmitters Final report mounted incorrectly 12/6/84 Not reportable 1

84-90 Reactor Vessel Snubber Final report 12/6/84 Not reportable

y w

[kh l/1%

l-l-

1 1

DER NO.

DESCRIPTION-CORRECTIVE MEASURES STATUS 4

84-91:

Piece of Metal Found in Final report' Unit 2 RCP 12/6/84.Not-reportable 84-93 Suppport' Rails in Panel Required bracing Final report.

B05 installed.

12/8/84-Reportable 84-96 Containment' Purge Valve Replacement of motor Final' Report Closure Time operators with pneumatic 12/7/84 operators Reportable-84-98 HFA Relay Contact' Contacts readjusted Final ~ Report Settings 12/14/84-Reportable 84-99 Regenerative Heat Bracket restored to Final Report Exchanger misaligned original configuration 12/14/84

= bolt holes Reportable 84-100' Compression. fittings on Inspected and tightened Final Report MCCs compression' holding 12/14/84 screws. Revised Reportable procedures.

'84-101 Containment purge valve Reinspection of all Final Report failure to'open applicable valves.

12/14/84 Installation of Loctite Reportable as required.84-102 Missing' tack welds on Rework of valves as Final-report

. Anchor / Darling swing required per A/D 12/14/84 check valves direction Reportable 84-103 Diesel generator roof Installation of hatch Final Report

-hatch restraints 12/14/84 Reportable 84-106 Spurious Load Shed of Replacement of sequencer Final report BOP ESFAS module and repair of 2/27/85 Not failed module reportable 85-01 Undersize taper pin on Inspection of various Final report AFP turbine bolts 6/6/85 I

Reportable 85-02 Silicon Controlled Final report Rectifiers Leakage 2/26/85 Not reportable i

}

I

[

I I

DER NO.

DESCRIPTION CORRECTIVE MEASURES STATUS 85-03 3-inch Seismic Gap Revision of procedures Final report Criteria 6/14/85 Not reportable 85-04 Type "A" fire damper Dampers fastened 1AW Final Report installation manufacturers 4/5/85 Reportable instructions 85-05 Improper installation of Rework / repair of all Final report bus fire stops nonsegregated phase 6/20/85 Reportable buses 85-07' CE instrument rack Addition of locking nuts Final report deficiencies new fasteners procured 9/9/85 Not to ASTM requirements reportable 85-08 Lov bysterisis'setpoint Froper setpoint Final report

-for AFAS initiation adjustment and 5/30/05 calibration 85-12' Cracking in-auxiliary Repair cracks by epoxy Final-report building valls injection 6/14/85 Not reportrble 85-14 L.ow lube oil trip of Rewire the four DG low Final report Emergency diesels lube oil trip contacts 6/14/85 Reportable 85-15 Thin wall pipe from None required Final report Hub, Inc.

7/15/85 Not reportable 85-16 Cracked spoke on AHU New hubs fabricated and Final report installed on AHUs 8/13/85 Reportable 85-19 High hydrazine flow rate Addition of stiffer Final report springs to Spray 7/25/85 Not Chemical Addition Fumps reportable discharge valves 85-20 Cracked rocker arm in DG Under evaluation Closed by RV 85-22 Colod-Coded Visual Inspect and clean all Final report indicators breaking off ARD relays and aux.

7/25/85 control relays and relay cabinets Reportable preventing travel 85-23 DG start failure due to Replacement of valves Final report mechanical valve failure 9/9/85 Not reportable

-l l

/.

l 1

j DER NO.

DESCRIPTION CORRECTIVE MEASURES STATUS 85-24 Broken DG turbocharger' Upgrade bolts and Final report bolts increase torque 9/13/85 Reportable 85-25 AFP on AFAS condition Under evaluation Closed by RV l

i 85-26

' Containment Purge System None required Final report i

9/11/85 Not

)

reportable

{

j 85-27 Pacific Scientific Pipe Increase in torque for Final report

')

clamps clamps 9/18/85 Reportable 85-32 Seismic separation Under evaluation Open between buildings.

j I

85-33 Bisco fire stops Under evaluation Open i

1 85-34 Failure of diesels to Under evaluation Open pick up loads in override i

l I

i 1

J o____________________-.____

j.

Part 21 Notifications All vendor Part 21 notifications have been reported and corrective action initiated by APS through Construction Deficiency Reports (10 CFR 50.55e).

k.

Construction Status The following safety-related and important to safety structures systems, and components are not complete as of October 8, 1985.

The remaining construction is reportedly relatively minor in nature consisting mainly of efforts to complete corrective actions identified as a result of testing, Deficiency Evaluation Reports, walk-down punchlist items, etc.

Description Subsystem Designator Boric Acid Condensate Ion Exchange CH09 Boric Acid Concentrator CH10 Containment Electrical and Spare Mechanical CLO6 Penetrations Containment Purge CP01 Fuel Carriage and Upender Fuel Transfer Tube FH07 Fuel Handling Tools FH08 Underwater TV Systems FH09 Refuel Machine FH10 CEA Change Platform FH11 CEA El'evator FH12 Fuel Pool Seal FH15 Sprinklers for Auxiliary Building FP21 Sprinklers for Lower Cable Spreading Room FP23 Deluge Sprinklers for Safety Injection Pump FP28 Sprinklers for Personnel Facilities FP30 Containment Building Hose Stations FP35 Halon Flooding Protection, Control Building FP36 Corridor Fire Protection FP39 Gaseous Radwaste GR01 Containment HVAC North HCO2 Pre-Access Air Filtration Unit ECO3 i

TMI Task HC70 l

Control Building Normal AHU RJ01 ESF Switchgear Room, Essential AHU "A" HJ02 i

ESF Switchgear Room. Essential AHU "B" HJ03 Battery Ventilation HJ06 Containment Hydrogen Control HP01 Containment Hydrogen Control System HP70 HVAC Exhaust HR02 Evaporator Package LR04 Concentrate Monitor Tanks LP05 Containment Radvaste Sump and Pump, West RD01 l

Containment Radwaste Sump and Pump. East RD02 Reactor Cavity Sump and Pumps RD03 1

,n Description Subsystem Designator RD04 Svap Pumps Discharge Heeder

- ESF Sump and Pumps'"A".

RDOS ESF Sump and Pumps "B" RD06 RD07 Non-ESF Sump and Pumps Radwaste Building. Sump and Pumps RD08 RD09 Holdup Tank Sump and Pumps Fuel Building Sump and Pumps RD10 Radioactive Waste Drain System-RD70

. Radioactive Waste Drain System RD71 Spent Resin Tanks'and Dewatering Pump SR01 SR02 Solidification Package.

Levels C&D (Auxiliary BuildinS)

ZA01 Pipe penetrations Rooms levels A&B ZA02 Valve Galleries ZA03 ZA06 Level A Pipeways & Chases Electrical Penetration Rooms Levels 1&2 ZA07 Level 1 Heat Exchanger Rooms ZA08 Pipeways, Valve Galleries ZA10

- Containment Building Persunnel Access Hatch Area ZA12 Level 3 Hot Lab,' Cold Lab, etc.

ZA14 Tendon.Ca11eries 2002 Level 3 Control Room ZJ01_

Corridor Vestibule and Airlock

.ZJ04 Stair'A for Levels 3&4, Vestibule and Roof _

ZJ08 ZJ11

- Upper Cable Spreading Room Cable Shafts' ZJ13

- Corridor and Stairs A on Level 1 ZJ16 Lower Cable Spreading Room Level 2-ZJ18 ZJ19

. Level 1 Switchgear Room

. Level A Air Handling Rooms.

ZJ20 Control Building and Auxiliary Building ZJ23 MSSS Elevation 80' ZM01 MSSS Elevation 100' ZM02 MSSS Elevation 120' ZM03 Controlled Machine Shop ZR01 ZR02 Level 1 Truck Bay

. Level 2 Radwaste Control Room ZR03 j

ZT07 Switchgear Room Level 1 Condensate Deck ZT13 Level 2 Mezzanine Deck ZT14 ZT17 Operations Deck Level 3

'The construction punchlist contains approximately 1500 detailed items as of October 8, 1985. Many of these items are expected to be resolved as a The licensee expects to resolve all of these items prior to fuel set.

load. Region V review of this list will be initiated once this list is reduced to a few hundred items.

,_r

1. Preoperational Test Results (1) Preoperational Testing - Preoperational testing will be completed on all safety related or important to safety systema prior to fuel load. The current status is as follows:

Total Tests Test Complete Test Results Approved 184 155 103 The remaining 29 tests that are not complete are listed below.

Test on Hold Percentage Procedure #

Description Complete 91PE-2CH09 Boric Acid Concentrator Test 85 91PE-2CP01 Containment Purge System 89 91PE-2GR01 Caseous Radwaste System 85 91PE-2HP01 Hydrogen Purge System 89 Test in Progress Percentage Procedure #

Description Complete 9'1PE-2FP02 Halon 1301 Fire Suppression System 80 91PE-2FP03 Carbon Dioxide Flooding Test 80 91PE-2HT01 Turbine Building HVAC 88 91PE-2LR03 LRS Concentrate Monitor Tanks 45 91PE-2RD01 Radioactive Waste Drainage System 70 91PE-2ZJ01 Polar Crane 80 92PE-2RJ03 Plant Honitoring System 85 92PE-2R102 Plant Annunciator System 87 92PE-2SB17 Auxiliary Relay Cabinet Test 88 93PE-2SD01 Field input Verification of Emergency 89 Resource Tests Not Started Procedure #

Description 91PE-ZFH01 (N)

Dry Sipping 91PE-2FH05 Refueling Machine 91PE-2FH06 Reactor Cora Indexing Preoperational 91PE-2FH09 Fuel Assembly Core Position Trial Test 91PE-2FH10 CEA Elevator and Change Platform Test 91PE-2HF02 Control Room Pressurization Test 91PE-2LR02 (N)

LRS Evaporator Package 91PE-2SR02 Solid Radwaste System 91PE-2SS02 (N)

Nuclear Cas Sampling Hydrogen and Analyzer Oxy 92PE-2FH01 Underwater Television System 92PE-2QF06 (N)

Preoperational In Plant Communications Test 92PE-2SB20 DNBR Calculator To PMS Data

4 92PE-2SQ01 Radiation Monitoring

)

93PE-2QD02 Modular AC Emergency Lighting Units 92PE-2SB19 QSPDS Preoperational. Test (N) Test prscedure not approved by licensee.

(2) System Acceptance - All safety related or important to safety 1

systems and areas will be accepted by operations to ensure drawings h

up-to-date and system completion prior to fuel load. The latest status is as follows:

i Total Subsystems Accepted Subsystems Walked Down 457 391 317 The remaining required subsystems yet to be walked down are FH-07-12 (Fuel' Handling), FP-35 (Fire Protection), QD-02 (Emergency Lighting),

QM-03 (Special Process Trace Heating), RD-01 (Radioactive Waste Drains), RD-06, RD-70, RD-71, RM-70 (Main Control Board,'RZ-70 (CRACS 6 PASS), SB-72 (Reactor Protection), SR-02 (Solid Radwaste).

Total Areas _

Accepted Walked Down 67 33 67 (3) Surveillance Test Procedures - The surveillance test procedures to be used at Unit 2 are the same as those currently being used at Unit 1 except for unit designation. Seventeen procedures remain to be corrected for Unit 2.

(4) Operations Procedures - With minor exceptions the operating procedures to be used at Unit 2 are the same as those for Unit 1 except for Unit designation. Three procedures remain to be conventive for Unit 2 use.

(5) S$gnificant System Performance Deficiencies During preoperational testing, the following deficiencies were notable:

Redesigned system to reduce High pressure safety injection valves malfunctioned differential press -

increased strength of electrical contact springs.

Microbiological corrosion of spray -

Improved chemical centrol.

pond distribution piping.

Frequency of recirculation increased and initiated a corrosion monitor program.

An engineering evaluation of Excessive heat loss from the primary system to containment was the condition is ongoing -

experienced durina the hot not expected to impact on functional test.

operations.

La :

~

~

' ' ' ' Cavit'ation detected in the Reversed the valve vicinity of the high pressure orientation and added an f

injection flow orifices and valves.

additional orifice

'{

downstream of-the existing orifice.

Monitor VCT level reference Loss of auxiliary spray due to trip of charging pumps after leg daily. Revise turbine trip / reactor trip /SIAS..

appropriate procedures-to align charging pump suction to RWT after Loss of Offsite Power. Acceptability of j

design under review by NRR.,

Unit 2 being hardwired.

Multiplexer malfunctioned causing trip of wrong breakers causing loss

' Acceptability.of design of offsite power.

under review by NRR.

l

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