ML16341B707

Forwards List of Remaining Open Items That Require Resolution Before Determination of Plant Readiness for Operation

ML16341B707
Person / Time
Site:	Diablo Canyon
Issue date:	07/23/1981
From:	Engelken R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:	Sniezek J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
NUDOCS 8107280256
Download: ML16341B707 (20)

Text

JUL R3 1981 gcarek-gum~: So-an5( 8~3 MEMORA(DUM FOR:

J.

H. Sniezek, Director, Division of Resident and Regional Reactor Inspection, IE FROM:

SUBJECT:

R. H. Engelken, Director, RV PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON UNIT 1 (DOCKET NO. 50-275)

>E Fir copy In accordance with inspection Procedure No. 94300B, the attached enclosures list the remaining open items that require resolution before finding of readiness for operation may be endorsed by Region V.

The format has been modified to identify items for each

Branch, and to separate items required for:

(1) fuel loading, (2) low power testing, and (3) full power operation.

Ollgtml Slgng gI R. L Engejken R.

H. Engelken Director Enclosur es:

Appendix A - Construction Items Appendix B - Operations Items Appendix C - Radiation Protection Items Appendix D - Safeguards Items cc w/enclosures:

H. D. 'Thornburg, Director, Division of Safeguards and Radiological Safety Inspection, IE:Hg B.

K. Grimes, Director, Division of Emergency Preparedness, IE:Hg CONTACT:

Phil Morrill FTS 463-3740 COSt 943-3740

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JUL 27198l' I @~ L~IORS Cl]

Distributed by RV:

RV PDR Resident Inspector State nf t'.A (HRh 8i0728025b 8i0723 PDR ADOCK 05000275 A

PDR n/johnson )

Sent to DMB for DCS processing.

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APPENDIX A CONSTRUCTION Outstanding Items - Action by applicant required before Inspection Procedures may be completed.

Bulletins FL LPT FPO (5X) (100')

IEB-79-02:

Pipe Support Baseplate Design Using Concrete Anchors (IE Insp.

Rpt. 50-275/81-10 covers)

Followu Items none 50.55 e

Items a.

Deficiency in containment Spray Pump Starting Sequencer b.

Potential deficiency related to low ultimate tensile values on 1" Hilti concrete anchors (see IEB 79-02) c.

120 VAC Power Supply Panel-Neutral Block FPO here is interpreted to mean prior to operation at power levels in excess of those for Low Power Testing.

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APPENDIX B OPERATIONS Outstanding Items - Action by applicant required before Ins ection Procedures ma be corn leted.

FL LPT FP Prep eration Tests (incomplete or not accepted by licensee) 3.7 Turbine Driven Aux FWP Initial Start and Perform.

Demonstration 8.4.1 Letdown, Charging, Seal Water 16.2 19.4

39. 1 Makeup Water System Flushing Spent Fuel Transfer System X

Containment Isolation Valves Leak Test Preop.

X Test

39. 3 Misc. Containment Leak Rate Test 7.5 Fuel Loadin and Power Ascension Testin (completion and/or acceptance by licensee required

~l 4.1 Calib. of Stm 8 FW.Flow Instrument 'at Power 4.6,

'team Gen'era4or Mois@re~ Carry'oker Measurement

'1 7.3

" Resistance Temper'ature'etector, Bypass Loop X

Flow Measurement P

Reactor Cool'ant Sys'em Flow Measurement X

(1)

(1) 7.6

7. 10

22. 8 Reactor Coolant System Flow Coastdown Pressurizer Spray 5 Heater Capability 5 Continuous Flow Setting Main Turbine Generator Initial Synch 5 Loading Procedure

22. 9

36. 1

36. 3

36. 5

36. 6

38. 1 Turbine Overspeed Test Rod Drive Mechanism Timing Rod Drop Time Measurement Rod Position Indication System Rod Control System Operational Test Automatic Reactor Control Operational Test

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APPENDIX B FL LPT FP

38. 2 Automatic Stm.

Gen.

Level Control Operational Test

38. 5 B-8D

41. 1

41. 2

41. 3

41. 4 41.5

41. 6

41. 7

41. 8

42. 1 Incore Moveable Detectors Initial Core Loading (Procedure Review 5 Approval)

Maintain Hot Shutdown From Outside Control Room Initial Criticality Nuclear Design Checks Rod 5 Boron Worth Measurement During Boron Dilution Rod 5 Boron Worth Measurement During Boron Addition Rod Control Cluster Assembly (RCCA) Pseudo Ejection at Zero Pwr Minimum Shutdown Verification & Stuck Rod Worth Measurement Dynamic Automatic Stm.

Dump Control Pwr Coeff 5 Integral Pwr Defect Meas.

During Pwr.

Level Increase (1)

(1) 42.2 RCCA Pseudo Ejection 8

RCCA Above Bank

"'osition Measurements 42.3

. Static RCCA Drop 8

RCCA Below, Bank Position Measurements" t

42. 4 Incore-Excore Detector, Cali,brati on 8(

i 42.5 Thermal Pwq Measurement 5 State Point Data

'Collection 1

42.8

'perational Alignment of RCS, Temperature Instruments V

(1)

(1)

I 42.9 Operational Alignment of Nuclear Instrumentation

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APPENDIX B

43. 1 Load Swing Tests FL LPT FP

43. 2

43. 3

43. 4

43. 5

43. 6

43. 7 Bulletins IEB 79-04 IEB 80-18 V

IEB 81-01 IEC 80-09 IEC 80-16 Net Load Trip Test Large Load,Reduction~*'Tests

'lant Trip from 100/ Power Rod Group Drop 8 Plant Trip VASSS 'Acceptance'Te'st-Net Load'.Trip. Test Crom-50Ã Powe'r.

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II and Circula'r's, Incorrect weights for.'Swing,.Check Valves Manufactu'red by Velan Engineering Corporation 1

Mainten'anceof, Adequate 'Minimum,,Flow thru

.Centrifugal Charging Pumps Following

,Sec'ondary'ide High 'Energy-Lin'e: Rupture fats

'P Surveillance of Mechanical'Siiubbers Problems with Plant Internal Communications Systems

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Operational Deficiencies in Rosemount Model 510DU Trip Units-8 Model 1152 Pressure Transmi tters (2)

(1)

(2)

(1)

(2)

(1)

X,

'~F11 801501 801701 801702 Surveillance Set Point for Lo-Lo SG LVL.

Trip Diff. from SER Supplement 9

Incorporate Procedures to Maintain Envr.

equals.

of Safe.

Rel.

XMTRS in Surv. Test Proc.

Oper.

Proc.

appear to conflict w/Proposed Tech.

Specs.

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APPENDIX B TI 2514 Ol Task Action Plan Items FL LPT FP I.A.2.1 I.A.2.3 1.C.1 I.C.8 I.G.1 II.B. 2 II. B. 4 II. D.3 II.E.1.2 II. E. 3.1 II. E.4.1 II.E.4.2 Immediate Upgrading of RO 5 SRO Training 8

Qualification (Items 1, 2, 3, 4 5 5, 0737)

Admin. of Training Programs for Licensed Operators (0737)

Short Term Accident Analysis 5 Procedure Revision (Items 2b 5 3b, 0737) to be completed by first refueling after 1/1/82 if license issued before 1/1/82.

Pilot Monitoring of Selected Emergency Procedures for OL Applicants (0737)

Training; Duririg Low Power Testing (Item 3, 0737)

(Licensee Tests

44. 1, 44.2, 44.3)

Reactor Coolant System Vents Procedures in Place by 1/1/82,.-Installation Complete by 7/1/82 (Items,2,5 3,. 0737:);, j

~..Plant-.Shielding, ('tem', '0737) Modifications Complete by;1/,1/82, z

(-',Training for<Miti'gating Core, Damage (See X

,, NU REG 0737.'or,ex'pl anati o'n )

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Rel ie f-'8'a fety".Valve."Indica'ti on (0737)

X Auxi'lia'ry Feedwat'er Ini'tiation 8 Indication X

"(-Items~la, 1b, 2a 8.2b,0737),-,.".

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,-.. Emergency Power for Pressuri'zer

.Heaters (0737) 1.

Conta'inment Dedicated Penetrations

- Hydrogen X

Control (Items 2 5 3, 0737) l'ontainment Isolation Dependability (Items 1

through 7, 0737)

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APPENDIX B TI 2514 OI Task Action Plan Items FL LPT FP II. F.2 Inadequate Core Cooling Instruments (Saturation X

Meter) Items 1

& 2, 0737)

( Item 4 completed by 1/1/82) lg II.G.1, Power Supplies from Emergency'Buses (0737) o ri III.D.1.1 Primary Coolant Sources Outside Containment (0737) i 50.55 e) Item,

Adjust steam generator low-'low water level trip set point per PGE letter dated 7/26/79.

Notes:

LPT here is interpreted to mean prior to initial criticality.

FPO here is interpreted to mean prior to operation at power levels in excess of those for Low Power. Testing.

J (1)

Tests conducted above 5~< power but prior to reaching lOOX power.

(2)

Tests to be conducted at or from 1005 power.

(3)

Other criteria as stated.

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APPENDIX C RADIATION PROTECTION Outstanding Items Action, by Appli'can't Required before Ins ection Procedures

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General Required for

FLp LPT FPO General empl oyee trai,ning and,,retrai,ning s

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'll Area radiation',monitors-", c'alibration

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1 Radioactive Waste S stems Process and;effluent monito'r calibration",(see IE Inspection-Report",50-275/81-.'09, and 81-05)

Incom lete Procedures'

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A-5 Liquid radwaste,discharge management-,." -,

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E-4 Outfall sampling G-11 Packaging, storage and inventory of solid, radioactive waste

.X Prep Tests - Incom lete or Not Acce ted 19.2. 12 Flush and preop spent resin system 19.4 Spent filter transfer systems 38.4 Radiation monitoring system Gaseous X

Process and effluent monitor calibration Incom lete Procedures A-6 Gaseous radwaste discharge management Prep Tests - Incom lete or Not Acce ted

23. 1 Main control room heating, ventilating and air conditioning system (complete)

Addendum 2 - Control room pressurization system

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APPENDIX C RADIATION PROTECTION LPT FPO Addendum 3 - Diesel exhaust effect on control room pressurization system 23.3 Preop test of logic controls for auxiliary and fuel handling building ventilation system 38.4 Radiation Monitoring System Outstandin Items - Ins ection rocedure com lete Reins ection re uired Radioactive Waste S stem C and Ca abilit Licensee has significantly modified laboratory instruments used in the"initial inspec'tion.'e-evaluation of gC an'd" Capability - advisable i

Outstandin Items - Not Previousl

- Ins 'ected r

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NUREG-0737 items re uired b

T12514 01-,Rev.

2 8 TI2515 44, Rev.

2 II.F.1 Additional Accident Monitoring Instrumentation III.A.1. 1 Emergency Preparedness Short Term III.A.1.2 Upgrade Emergency Support Facilities III.D.3.3 Inplant Radiation Monitoring II.B.3 Post Accident Sampling III.A.2 Emergency Preparedness

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APPENDIX D SAFEGUARDS:

Re uired 30 da s

rior to fuel 1oadin IE Bulletin 79-16:

Based on a review of the licensee's reply actions appear to be adequate

- however this item remains open until actual implementation of the security program.

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11 d t d 3/28/13 4/6/79 the physical security program as implemented at that time was found to be inadequate in most inspection areas.

(Inspection Report 50-275/79-09 (IE-U-298)).

Determination of adequacy of'he physical protection program will remain open until fully implemented by the licensee and subjected to full NRC preoperational inspection.

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hpt 2313 81 ht p

3 inspection for material control and accounting be started no earlier than 3 months prior to, or completed no later than within 30 days prior to, the issuance of an operating license.

Based on earlier expectations for issuance of the Diablo-I operating license, material accountability inspections were conducted in February 1976 (Report Number 7601) and March 1979 (Report Number 7901).

In each instance, material'ccountability provisions were found to be adequate.

A future inspection as necessary to meet Chapter 2513 guidelines will require about 16 man-hours of inspection effort.

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