ML20147H020

Draft Summary Rept for Regional Evaluation of Texas Utils Generating Co,Comanche Peak Steam Electric Station

ML20147H020
Person / Time
Site:	Comanche Peak, 05000000
Issue date:	06/30/1983
From:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20147G863	List: ML20147G859 ML20147G870 ML20147G915 ML20147G948 ML20147G990 ML20147H005 ML20147H010 ML20147H020 ML20147H033
References
FOIA-87-847 NUDOCS 8803080365
Download: ML20147H020 (23)

Text

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SLf4 MARY REPORT  !

FOR  !

REGIONAL EVALUATION OF TEXAS UTILITIES GENERATING COMPANY CCriANCHE PEAK S.E.S DOCKET 50-445 PREPARED BY U. S. NUCLEAR REGULATORY COMMISSION REGION IV

JUNE 30, 1983 i .

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., Ouring the period of August 1,1979 through July 31, 1980, this facility

was evaluated in the following functional areas: ,

Functional Area Increase No. Change Decrease l Quality Assurance, Manage-ment & Training X l

Substructure & Foundations complete .

. Concrete X Liner (Containment & Others) complete Safety-Related Structures X Piping & Hangers (Reactor Coolant & Others) X Safety-Related Components (Vessel, Internals & HVAC) X Electrical E X Electrical (quipmentTray & Wire) X i Instrumentation X i Fire Protection X 1

Preservice Inspection X Reporting X >

During the period of July 1,1980 through June 30, 1981, this facility was evaluated in the following functional areas:

Functional Areas Ca tegory Soils and foundations NA Containment and other Safety-Related Structures NA Piping Systems and Supports 1 Safety-Related Components 1 Support Systems 2 Electrical Power Supply and Distribution 1  :

Instrumentation and Control Systems 1  :

Licensing Activities 2 ,

4 During the period of October 1,1981 through September 30, 1982, this facility was evaluated in the following functional areas:

Performance Category Functional Area 1982 l

.' 1 A. Plant Operations - Preoperational 1 Testing 3 i B. Construction Activities ,

Soils and Foundation N/E  ;

i Containment and Other safety-Related '

j Structures 2 i

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Piping Systems and Supports (includes welding, NDE, and preservice inspection) 2 Safety-Related Components (includes vessel, internals, pumps,etc.) 1  :

SupportSystems(includesHVAC,radwaste. l fire protection) N/E Electrical Power Supply and Distribution 1 Instrment and Control Systems 1 Vendor Procureinent Cycle Controls 3 Licensing Activities 1 D. ESCALATED ENFORCEMENT HISTORY An Immediate Action Letter was issued on September 7,1979, confirming a licensee decision not to place concrete in the wall to dome transition area of the Unit 2 Containment Building until such time as a proper engin-eering evaluation could be made of the omission and subsequent addition in another location of a group of reinforcing steel shear ties.

E. INDEPENDENT DESIGN HISTORY _

Oiscussion with licensee are in progress. No final decision has been reached.

F. NRC INDEPENDENT MEASUREMENTS INSPECTION The NRC Mobile NDE Laboratory was brought to The Comanche Peak site April 25 - May 6,1983. The report on the results of the examination has not been released. When the report is released, it will be included as an addend s to this report.

G. GENERIC CORRES.P_0NDENCE TUGC0 has established procedures providing specific instructions to the nuclear project support group personnel who are responsible for coordina- e tion and review of IE Circulars, Bulletins, and Generic Letters. In each case, a TUGC0-appointed coordinator is given responsiblility for assigning the cognizant responsible person to review and track all actions and provide doc mentation. When required the coordinator shall draft a res-ponse to tha NRC which will be reviewed by plant manager-nuclear, licensing engineering supervisor-nuclear, and project support manager-nuclear. The response shall be signed by the vice president-nuclear operations and shall include an affidavit. A permanent record of actions taken is maintained.

H. LICENSEE AND CONTRACTOR INITI ATED STOP WORK ACTION There have been 45 stop work orders issued by the licensee and his contrac-tors. See Exhibit 2 for a summary of the stop work orders.  !

I. CONSTRUCTION DEFICIENCY REPORTS (10 CFR 50.55e)  ;

The licensee has reported 34 significant construction deficiencies. See l Exhibit 3 for a summary of these reports. l

4 J. PART 21 NOTIFICATIONS Part 21' Reports are being handled as 10 CFR 50.55e item and will appear in .

Section ! of this report.

K. NRC INSPECTION ACTIVITIES

1. Construction Inspection The routine MC 2512 inspection program is essentially complete for Unit 1 and Comon, however, an augmented program has been implemented to correspond to licensee final completions inspection. This special pro-gram is the key to actual activities of completion and will be on-going until final construction completion.

2. Preoperational Testing and Operational Preparedness MC 2513 is directed toward inspection of activities involved in preoper-ational testing and operational preparedness. These inspection activities may be sumarized as follows:

1 Complete Preoperational Test Procedure Review 95 Preoperational Test Witnessing 50 Preoperational Test Results Evaluation 25 ,

Operation Staffing '

0 Quality Assurance 80 Operating Staff Training 75 Technical Specification Review 20 Operational Procedure Review 0 6 Radiation Protection .

50 Ra'dwaste 50 Environmental Monitoring 50

. Emergency Planni.ng . 50 Security 50

3. Startup Testi.ng 1

i inspection activities established in MC 2514 define the inspection

! prograni for the startup testing phase. Since this program generally l starts with fuel loading, the program, except for procedure review,

has not begun. The program includes

l ec ical Specification Review (started in MC 2513)

Startup Procedure Review

Initial fuel Load Precritical Checks Power' Ascension Testing Initial Criticality / Low Power Testing Data Review

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4. TMI Open Items Most of the TMI lessons-learned issues were specifically addressed during the FSAR review and appear in The Safety Evaluation Report, Nureg-0737 and its supplements. These items are being tracked and verified during preoperational testing (MC 2513). The individual items will be inspected and closed out in accordance with the temp-orary instruction.

5. Allegations Numerous allegations specific to Comanche Peak SES have been received during the last two years, in part due to the public licensing hearings.

Several of the investigations of these allegations is on-going at this time.

6. NRR Confirmatory Items (To be verified by Region IV program)

SER Section Description of Item 5.3.1.2/5.3.1.3 Fracture-toughness properites of Unit 2 5.3.2/5.3.3 reactor vessel materials (SSER #1 5.3.1.2, 5.3.1. 3, 5.3.2, and 5.3.3) 7.3.2.2 Steam generator reference leg temperature compensation and low-low steam generator level setpoint per IE Bulletin 79-21 7.5.4 Confirmation of procedure review per IE

• Bulletin 79-27 9.1.4 Handling of heavy loads in conformance with the guidelines of NUREG-0612 (SSER #1 9.1.4) 10.4.5 Protection against folding of safety-

• related compartments from a failure in the circulating water expansion joint 9.4.4 Verification that auxiliary building post- i LOCA radiation levels will be low enough  !

to permit manual operation of exhaust i damper CPX-VADPOC-83 22 TMI Action Plan I.C.2 Shift and relief turnover procedures  !

(SSER#1) l l

I.C.5 Procedures for feedback of operating exper-

) ience to plant staff (SSER #1)

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. l I.G.1 Special low-power testing and training l II.B.1 Reactor coolant system vents 11.0.1 Perfonnance testing of BWR and PWR relief  :

and safety valves (SSER #1)

II.E.1.1 Reconinendation GL-3: Verification by test of the capability of the turbine-driven AFW pump to operate for two hours without ac power II.E.4.2 Containment isolation dependability I I . K. 2.13 Thermal mechanical report--effect of high-pressure injection on vessel integrity for small-break LOCA accident with no auxiliary feedwater (SSER #1)

II.K.2.17 Potential for voiding in the reactor cool-ant system during transients (SSER #1)

II.K.3.1 Installation and testing of automatic PORY isolation system (SSER #1)

II.K.3.2 Report on overall safety effect of PORY isolation system (SSER #1)

!!.K.3.5 Automatic trip of reactor coolant pumps during LOCA II.K 3.11 Justification of use of certain PORVs I (SSE.R' #1)

. II.K.3.30 Revised small-break LOCA methods to show i compliance with 10 CFR 50, Appendix K l II.K.3.31 Plant-specific calculations to show com-pliance with 10 CFR 50.46

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SSER Section Descr'iption of Item 3.9.6 Periodic leak testing of pressure isola-tion valves -

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9.5 Documentation of applicant's commitments l on fire protection l I

L. CONSTRUCTION STATUS i l

The active systens have largely been completed sufficiently to conduct pre-  !

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7 operational tests. Pipe support design and installation remain as major pacing effort at this time. Also, there is a considerable effort in the area attaining separation in the electrical area. (IEEE 384)

There is also a considerable effort directed to engineering design review of site changes. In conjunction with this effort, site QA is verifying that the changes have been inspected and that proper documentation is available.

M. PREOPERATIONAL TEST RESULTS The TUGC0 startup group has detennined that the plant will be safe for fuel load when the following systems have been prerequisite /preoperational tested. Not all systems are required to be preoperational tested by NRC Regulatory Guide 1.68, Revision 2.

Preoperational System Description- *% Complete 01 125 Y DC Class 1E Power Systems 50 02 6.9 KV/480v Class 1E AC Distribution Systems 85 03 Startup Power Systems 90 04 Service Water System 90 06 Fire Protection / Detection Systems 25 07 Control Room - HVAC System 60 08 Battery Rooms - HVAC System . 50 11 Component Cooling Water System 90 12 Coanunication System 0

22 Sampling System 80 24 Primary Plant Ventilation System 75 29 Diesel Generator and Auxiliaries System 90 31 Safety Chill Water System 100 32 Auxiliary Building - HVAC 100 34 Main Steam System . ,

90 1 36 Safeguards Building - HVAC System 80 37 Auxiliary feedwater System 90 39 Diesel Generator - HVI.C Systen . 100 40 Fuel Handling and Vessel Servicing Systems 55 41 Liquid Waste Processing System 0 2 42 Fuel Building.- HVAC System 90 44 Steam Generator Blowdown System 100 45 Containment Ventilation System 85 46 Containment Hydrogen Purge System 65 47 fuel Pool Cooling and Cleanup System 100 48 Containment Spray System 75 49 Chemical and Volumn Control System 80 55 Reactor Coolant System 85 56 Boron Recycle System 75 57 Safety injection System 30 58 Residual Heat Removal Systen 85 60 Solid Waste Processing System 45 61 Gaseous Waste Processing System 0

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Reactor Protection System 40

, 64 0 65 Containment Atmosphere Monitoring System Nuclear Instrumentation System 0 66 50 67 Hydrogen Recombiner System Rod Control System 0 1

68 0 70 Radiation Monitoring System Protection and Surveillance Package (N-16) 0 73 90 74 Movable Incore and Flux Mapping System Structural Integrity and Leak Rate Testing 90 4

75 0 78 ERF Computer (SPDS) System Seismic Monitoring System 50 80 50 81 Cranes and Hoists 0 82 Meterological fionitoring System Loose Parts Monitoring System 100 91

• 90% indicates the physical testing is complete with the remaining 10%

allowed for review and acceptance of test results.

The preoperational test program is 63% complete.

There are 10 properational tests that are in the draft form stage. They are listed below along with their scheduled completion dates.

4 1CP-PT-02-06 Annunciator Operability Test 7/18/83 1CP-PT-02-17 6.9 KV and 480 B SWGR Under .

Voltage Functional Test 5/28/83 1CP-PT-06-04 Charcoal Filter Deluge 7/18/83 1CP-PT-49-06 Boron Dilution Midigation 6/27/83 ,

1CP-PT-57-10 Pedundant Class 1E Trains ,

Integrated Safeguards Actuation Independence Test 9/15/83 1CP-PT-64 -01 RPS Time Response Measurement 6/6/83 1CP-PT-64-04 Reactor Plant System Setpoint Verification 7/18/83 1CP-PT-64-08 RPS Time Response Summary 6/27/83 1CP-PT-66-01 Nuclear Instruentation System 6/6/83 1CP-PT-70-02 Report Process System 7/25/,83 i

II. CONCLUSION _

The licensees performance and progress has generally been on par with other utilities embarking on their first nuclear facility. The upper management exhibits keen interest and support for Comanche Peak S.E.S.

However, like other first time nuclear utilitier, they have been hampered

by the lack of actual nuclear experience.

! The licensee has offically scheduled fuel load for Unit 1 in September of 4

1983. The assessment of the Regional Office, based on work to be done and the past progress rate, estimates that fuel load can take place no sooner than December of 1983, i

The licensee's Quality Assurance program for design, construction, pre-l operational, and startup programs appears adequate to assure the necessary confidence level for these programs are attained.

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EXHIBIT 2 STOP WORK HOTICES ,

Page 1 START WORK ISSUED TO ISSUED DATE SUBJECT APPROVAL DATE DISPOSITION Construction 07/26/75 Category 1 Concrete Pours 08/01/75 - Testing lab implemented their quality program to correct deficiencies and prevent recurrence Chicago 09/03/75 Work on containment liner 09/04/75 Performed HT examination in Bridge & Iron Co. which precludes radiography lieu of RT on reactor cavity containment liner.

Ccnstruction 12/19/75 Category 1 Concrete Pours 12/22/75 Provided clarification of discrepancies noted on

- surveillance report Const uction 12/23/75 Concrete Aggregate 12/30/75 Mixed aggregates frou several locations to provide a composite aggregate that met requireuents Construction 02/12/76 Category 1 Concrete Pours Varied with Planning impleeted in complexity accordance with Reg. Cuide

, 1.55 Construction 04/28/76 Off-loading of volume control 04/29/76 Obtained purchase order tank Construction 07/23/7b On site misdEllaneous steel 68/03/76 Revised inspection procedure fabrication on Safety Related Items Construction 07/23/76 On site miscellaneous steel 07/29/76 Revised inspection procedure installation of safety related

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STOP WORK NOTICES Page 2 1

START W(MK ISSUED TO ISSUED DATE SUBJECT APPROVAL DATE DISPOSITION Construction 08/02/76 On site miscellaneous steel 08/05/76 Revised inspection procedure fabrication of safety related i teus Construction 08/20/76 Receiving Safety Related 09/16/76 Issued procedure for Mechanical Equipment that surveillance of maintenance Requires Maintenance of mechanical equipeent Construction 08/20/76 Receiving Safety Related 09/16/76 Issued procedure for Electrical Equipment that surveillance of maintenance Requires Maintenance ,

of electrical equipment R. W. H2nt Co. 11/18/76 Calibration Activities 02/15/77 . Established and implemented an acceptable program Construction / 11/30/76 Calibration Activities 02/14/77 Established and fwplemented Quality Assurance an acceptable program Construction 01/24/77 Calibration of Optical Field 01/27/77 Corrected discrepancies Survey Instruments Engineering 07/01/77 Design change document None Discontinued practice of legibility telecopying design changes Bostran 07/12/77 All safety related work by 08/10/77 Supplier corrected survey Dergen Co. Bostrom Bergen in Fresno deficiencies arms was resurveyed Construction 07/21/77 All Safety Related activities 07/29/77 Corrected docesent control at miscellaneous steel fab shop deficiencies l

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. STOP WORK NOTICES Page 3 START WORK ISSUED TO ISSUED DATE SUBJECT APPROVAL DATE DISPOSITION Construction 07/21/77 Concreting of enbedded anchor 08/01/77 Established accountability bolts in Unit 1 Contalmeent 8 of the anchor bolts Engineering 07/28/77 On site issuance of field 08/01/77 Establist.ed appropriate design changes management controls '

Construction 07/28/77 Safety Related Construction 08/01/77 Implemented procedural activities affected by all requirements field design changes issued to date i .

Construction 08/19/77 , Installation of safety 09/09/77 Resolved adt.iinistrative related piping concern Construction 01/17/78 - All welding associated with 01/25/78 Flowmeters and welding ASME activities machines were- checked for specified output and the checks cocuriiented ana

, traceable to each machine Bahnson 04/18/78 All Fabrication or Installation 05/10/78 Resolved surveillance Service Co. of any Nuclear Safety Related findings Category 1 items or assenblies Construction 08/2S/78 Welding of stainless steel Case basis Established progran for -

rr.s ta.*i al s closer monitoring of

, welders to assure proceaural corap! lance Construction 09/05/78 Safety Related Welding 09/19/78 Revised Welder Conformance Qualification Log and updated

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QA records to reflect welder .

qualification status '

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. STOP WORK NOTICES Page 4 i.

START WORK ISSUED TO ISSUED DATE SUBJECT i APPROVAL DATE __

DISPOSITION Construction / 10/17/78 Grigination, distribution and 10/19/78 Revised procedures to Engineering all work performed to all adequately describe the project 04C's method (s) used for the origination, distribution, and use of CMC's.

Indoctrinatea project

personnel Construction 10/23/78 Unauthorized repairs in ll/lb/78 Evaluated welds for Unit I main loop piping acceptabli ty.

Investigated cause of

unauthorized repairs and took appropriate taanagement actions.

Construction 10/30/78 Manual welding activities 11/30/78 Perfonned analysis of associated with the Unit I welding materials with mi.in loop piping satisfactory results 1

Construction 02/14/79 We lding - ASME on WP5 88023 - 02/16/79 Requalified procedure Question on procedure qualification Construction 02/15/79 Welding - ASME on WPS 33021 - 02/15/79 Corrected discrepancy Through wall repairs Construction 04/13/79 Welding - ASME on WPS 88023 - 04/16/79 Corrected docuaentation

. Question on procedure discrepancy qualification documentation Construction 10/19/79 Housekeeping in safety- 10/22/79 Accomplishea cleanup and related buildings established ongoing prograia 9

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STOP WORK GuTICES Page S i

. START WORK ISSUED TO ISSUE 0 DATE SUBJECT APPROVAL DATE UlSPOSITIQ1 Construc tion ' 10/26/79 Installation of Sway Strut 02/21/80 Design drawins to be included Assemblies in traveler package, indoctrinated personnel in assembly, and provided inspection criteria Construction 10/29/79 All Class IE and associated 12/03/79 Cable pu! ling lubricant Class IE cable pulling activities tested ane detennined to be acceptable Construction 07/09/80 Fabrication and installation 07/25]80 Established and implemented of Class V Pipe Supports an acceptable program Construction 07/2S/80 Procurement, fabrication and 01/30/81 Established and implemented installation of secondary an acceptable program restraints for esseatial lighting and ligh' conduit '

Engineering 08/01/80 Design of small bore pipe 09/03/80 Established and implemented supports an acceptable prograa Construction 01/20/81 Epozy grouting of base plates .09/30/81 Acceptable grout selected Engineering 01/30/81 Field design changes for 02/02/81 Established and implemented pipe supports appropriate procedural controls MATSCO 01/IS/82 Lack of responsiveness to 05/04/82 Resolved deficiencies to QA hsdit Deficiencies BIF 03/03/82 Nuclear QA Progran not None Material scrappea and implemented by supplier repurchased from alternate 50urC0

STOP WORK N0fICES Page o START WORK ISSUED TO ISSUED DATE SUBJECT APPROVAL DATE DISPOSITION RAPC0 07/19/82 Corrective actions from 08/12/82 Resolved discrepancies previous audit nc+c implemented Chicago 08/10/82 Lack of compliance to 08/11/82 . Established poe.itive Bridge & Iron speci fication requirements corrective action for pipe whip restraints Quality Control / 11/23/82 Liquid Penetrant Examinations 02/09/83 Recalled all penetrant Welding Enginer ring materials and issued approved penetrant Bahnson 03/08/83 Structural Welding; HVAC 04/27I83 Upgraded inspection program Service Co. Supports and indoctrinated affected personnel TUGC0 Operations 04/1S/83 Audit deficiencies with 04/19/83 Established positive Instrumentation and corrective action and Control Activities i_ .

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Pd9" 1 CEXHIBIT 3 REPORTABLE SIGNIFICANT DEFICIENCIES NUMBER DATE SUBJECT ,

DISPOSITION 2/4/75 Unit 1 Reactor Building Excavation Fractured rock Removed and replaced with dental (Overbreak) concrete and grout.

1 7/24/75 Unit 1 Reactor Cavity Mat (Cold Joint) Concrete removed; new joint prepared.

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4/9/76 Unit 1 Containment Base Mat Coring Concrete integrity determined acceptable through coring and core holes filled with grout or mortar.

- -- 9/20/76 SSI Dam Filter "A" Material Removed nonconforming Filter "A" material and other conforming portions of the dam. Reconstructed dam.

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77-4 5/6/77 Weld Defects in Polar Crane Brackets Rework all similar welds and perform random (Tr inspection on all other welds.

77-C 7/19/77 Westinghouse AR Relays All affected contact cartridges replaced with approved relays and torque requirements placed on holddown screens 77-D 9/29/77 Westinghouse Operation of Safeguard Deficiency identified and corrected prior to receipt Actuation Block / Reset Circuitry at CPSES.

Place hold on drawings issued to contractor and redesi 77-B 8/23/77 Design Deficiency in Fuel Building Crane l ,

System support structure to incorporate correct seismic loadings.

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79-5 Pipe Wall' Thickness May Not 'Aee! ASME Determine wall thic ess by documentation review and/c 5/22/79 Code Stress Requirements UT inspection. All Class 1 piping with less than minimum wall will be repaired. All other piping great

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REPORTABLE SIGNIFICANT DEFICIENCIES i.

NUMBER DATE SUBJECT DISPOSITION 79-6 6/19/79 Electrical Cable Tray Hangers without After review of 404 cable tray hangers assigned to CBC Full Penetretion Welds 210 are to be reworked per Engineering direction.

79-8 11/7/79 Installation of Drilled in Expansion Anchora Revise procedures to reflect correct installation re-quirements, identify affected supports, rework as required.

i 79-9 11/15/79 Installation and Inspection of Welded Devel0P typical engineering drawings & provide additio Conduit Supports - information on construction travelers. Develop in-spection procedures and reinspect supports to provide documentation.

79-10 11/20/79 Class V Pipe Supports Revise PSAR to delineate requirements for supports, revise specification to clarify quality requirements, develop and implement construction s inspection proce-dures, reinspect, and rework as necessary 79-13 12/13/79 Concrete Honeycombs Unit 2 Steam Determine defective areas and repair Generator Compartments I

80-02 2/22/80 Discs for SW Control Valves Return to vendor for repair / rework.

80-03 2/29/80 Welded Connection of Control Boards Review as-built weld configuration and rework as necessary 80-05 ,7/2/80 Two Inch Architectural Concrete in Floor NCR M-81-01667 issued against non-conforming bolts.

Slabs 80-09 ,9/26/80 Diesel Generator Pipe Supports Establish compliance to requirements by engineering l

evaluation, inspection and rework if required.

P&ge 3 REPORTABLE SIGNIFICANT DEFICIENCIES NUMBER DATE SUBJECT DISPOSITION 80-10 10/1/80 Hilti Kwik Bolt Installation Indoctrinate personnel, rework affected supports, and initiate a sampling program of UT examination for Hilti-bolt installation 81-A 2/17/81 Westinghouse Gate Valves Modify valves as per Westinghouse Field Change Notice and perform stroking during startup testing.

81-B 3/24/81 Bahnson HVAC Anchor Bolts Revise Bahnson Procedures to require information on anchor bolts, as-built drawings, reinspect previous i stallations and document as as-built dwgs for post in stallation design verification. Rework as necessary.

81-03 3/30/81 HVAC Cooling System Replace existing HVAC system with system meeting new l design requirements.

81-06 6/4/81 Seismic Design Criteria for Instrumentation Evaluate engineering documentation and revise, if Supports necessary, survey completed installations and rework as required.

81-07 11/19/81 Orifice Plates (BIF) Outside ISA Standard Scrap existing orifice plates and procure new plates RF3.2 Tolerances from a new supplier with an approved quality program.

82-A 1/22/S2 Borg Warner Valves May Not Close Properly Rework / repair if Installed Between 22bo & 157 0 I .

82-02 2/25/82 Papco HVAC Fire Damper Dampers will be cleaned & lubricated, blade locks see with additional fasteners, damaged closure springs re

, l .placed & based on testing additional springs added, 6 l

large horizontal dampers replaced with nultipanel dmp 82-07 8/12/82 Governor Drive Coupling Existing drive element to be replaced with new elemen

. of more suitable material (neoprene) .

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REPORTABLE SIGNIFICANT DEFICIENCIES NUMBER DATE SUBJECT DISPOSITION 82-09 8/18/82 Solid State Protection System Undetectable . Modify test procedure.

Failure (Westinghouse 10CFR21) 83-01 1/20/83 Fractured Tack Weld in Check Valve Valves redesigned to change tack weld to fillet weld, cisassemble, inspect & repair valves supplied prior t design change.. Inspect valves supplied after design change to insure correct weld.

83-02 1/25/83 Westinghouse Gate valves Modify valves in accordance with manufacturer's recommendations.

83-07 3/10/83 New Fuel Storage Racks Approved anchor design issued and racks reworked.

83-08 3/24/83 Valves Without. Proper Weld Documentation Scrap existing brackets and replace 83-09 4/20/83 DS-416 Reactor Trip Switchgear Replace i

83-11 5/24/83 CCW System Class V Piping Controls added to existing level transmitters and non-safety related components upgraded.

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