IR 05000275/1986001

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Insp Repts 50-275/86-01 & 50-323/86-01 on 860113-17.No Noncompliance or Deviation Noted.Major Areas Inspected: Followup of IE Bulletins & Notices,Part 21 Repts,Other Open Items & Plant Tours
ML17083B705
Person / Time
Site: Diablo Canyon  
Issue date: 02/04/1986
From: Burdoin J, Dodds R
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
To:
Shared Package
ML17083B703 List:
References
50-275-86-01, 50-275-86-1, 50-323-86-01, 50-323-86-1, IEB-85-001, IEB-85-002, IEB-85-1, IEB-85-2, IEIN-85-066, IEIN-85-66, NUDOCS 8602250124
Download: ML17083B705 (12)


Text

U. S.

NUCLEAR REGULATORY COE1ISSION

REGION V

Report Nos.

Docket Nos.

License Nos.

Licensee:

50-275/86-01 and 50-323/86-01 50-275 and 50-323 DPR-80, DPR-81 Pacific Gas and Electric Company 77 Beale Street, Room 1451 San Francisco, California 94106 Facility Name:

Inspection at:

Diablo Canyon Units 1 and

Diablo Canyon Site, San Luis Obispo County, CA Inspection conducted:

January 13-17, 1986 Inspector:

. F.

B r'd in, Reactor Ispector z8'

D te Signed Approved By:

R. T. Do ds, Chief, Reactor Project Section

1 te Signed Summary:

Ins ection durin the eriod of Janua 13-17 1986 (Re ort Nos. 50-275/86-01 and 50-323/86-01)

Areas 'Ins ected:,

Unannounced inspection'by one regional inspector consisting of followup of IE Bulletins and Notices, Part 21 Reports, other open items and plant tours.',Inspection procedures:numbers 36100, 92701, and 92703 were used as guidance'for th'e inspection.

The inspection involved 36 inspection hours by one inspector.

Results:

No items of noncompliance or'eviations were identified.

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.DETAILS l. " Individuals Co'ntacted, Pa'cific Gas-and,.Electric

!Com an (PG&E)

"<R; C. Thoriibe'pry, Plantl Ma'nager

'"R. Patterson, Assistant"Plant'Manager, Plant Superintendent R.-D., Etzler,'onstruction" Superintendent

, D.,A. Rockwell, Assi'stant Zield Construction Superintendent D. R. Bell, QC Supervisor

D.-A.'Taggart, Acting Director, Quality Support QA W.,E. Coley, Lead Startup,.Engineer J.

R. Bratton, Rate Case Coordinator W. J. Kelly, Licensing Representative-T. L. Grebel,'egulatory Compliance Supervisor

+R. L. Johnson, Licensing Representative f

R. L. Watson, Supervisor, Quality Support R.

W. Cook, Rate Case Group Coordinator M. I,. Horseman, Quality Support Engineer Various other engineering and QC personnel.

="Denotes attendees at exit management meeting on January 17, 1986.

In addition, NRC Resident Inspectors attended the exit management meeting.

2.

Area Ins ection An independent inspection was conducted in Units 1 and 2 areas., In the auxiliary building, the equipment spaces inspected included six charging pump areas, six component, cooling water pump areas, four RHR pump areas, four safety injection pump areas, and two containment spray pump areas (Unit 2 only).

The refueling level (elevation 140 ft).of Unit 2 containment was inspected.

Housekeeping and equipment, status appeared to be satisfactory, particularly, oil level for pump gears/bearings appeared satisfactory and no excessive oil accumulation was identified.

3.

No violations of NRC requirements were identified.

Licensee Action on IE Bulletins/Notices a.

(0 en) 50-275/50-323 IE Bulletin 85-01 Steam Bindin of Auxiliar Peedwater Pum s

This bulletin informed licensees of a potentially serious safety problem involving the inoperability of auxiliary feedwater (AFW)

pumps as a result of steam bindin I t

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'I The bulletin',action required the licensee to:

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Develop procedure for monitoring fluid conditions within the AFW system on a regular basis during times when the system is required to be operable.

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Develop procedures for recognizing steam binding and for restoring'he

'system: to operable status, should steam binding occur.

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Main'tain pro'cedural controls in effect until completion of h'ardware 'modifications to substantially reduce the likelihood

'o'f steam bi'ndi'ng or, until superseded by action implemented as a

result of resolution of Generic Issue 93.

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'I The status of this'bulletin was reviewed with the licensee and the necessary proc'edures",w'ere being prepared.

This"item will remain open and;will be followed up as open item XB-85-01.

b.

(Closed) 50-275/50-323 IE Bulletin 85-02 Undervolta e Tri Attachments of Westin house DB-50 e Reactor Tri Breakers (RTBs)

This bulletin informed licensee, operators of Westinghouse plants, of recent reactor trip breaker reliability problems, to assure that licensees who have not yet installed the automatic shunt trip modification, are performing undervoltage trip attachment (UVTA)

force margin testing, and to clarify the "OPERABILITY" requirements related to RTBs.

The inspector reviewed this bulletin with the licensee and determined that the modifications for implementing the automatic actuation of the shunt trip coil of the reactor trip breakers for all automatic reactor trip signals had been accomplished for both units.

The inspector verified the completion of this modification work by reviewing the DCNs (DCl-EE-13620/DC2-EE-14620)

under which the work was performed and reviewing the QC completion records (E53-2118/2064) attesting to the completion of the DCNs.

It was concluded that the actions called for by this bulletin had been completed for Diablo Canyon Units 1 and 2 prior to the issuance of the bulletin.

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The bulletin is closed for Units 1 and 2.

(0 en) 50-275/50-323 IE Notice 85-66 Discre ancies between As-Built Construction Drawin s and E ui ment Installations This Notice informed licensees of a potentially significant generic problem regarding as-built construction drawings not correctly or completely reflecting equipment installation '

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Part 21 Item The licensee's quality assurance group, at t:he plane examined the drawings/sketches from three-DCNs>t'o'dete'rmine,if field

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installations matched as-built'drawings."

A,;few"discrepancies were found, and these were being'examined by'he'icensee to determine if a generic issue exists at the, Diablo pl'ant.

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This item will remain open and will be, followed's",,open 'item IN-85-66.

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(0 en) 50-275/323/85-19-P, Part

S eed Increaser IGear Drive (Model SU-1023-8X and SU-16-10)

Lube Oil Pum Cou lin Ke a /ke The licensee of the Trojan plant reported under

CFR 21 that during maintenance inspection of the speed increaser gear drive on the "B" train centrifugal charging pump, it was discovered that the low speed shaft coupling key for the lube oil pump had traveled,,in the keyway.

This could have resulted in disengagement of the speed increaser lube oil pump which would have failed the speed increaser due to lack of proper lubrication.

The model SU-1023-8X speed increaser is used on the centrifugal charging pumps and the model SU-16-10 speed increaser is used on the diesel driven auxiliary feedwater pump at the Trojan plant.

The licensee became aware of this concern through the "network" (operating plant experiences)

last fall and initiated an investigation/corrective program to determine if these types of speed increasers were used at Diablo Canyon; and if so, corrective action will.be initiated.

This. item will be followed as open item 85-19-P.

5.

Follow-u on Previous Identified Ins ection Items (Closed)

50-323/TI-12-03 This item requires verification of compliance with ASME certification system requirements.

The requirements and responsibilities of the ASME Code concerning obtaining of certificates of authorization and code stamping of items have experienced numerous changes from the time of initial design in the mid sixties till the construction of Unit 2 was completed in early 1985.

During the early stages of design and construction (mid 1960's),

the design of applicable parts, components, and installation were conducted in accordance with ANSI B31.1 power piping and B31.7 nuclear power piping.

The two contractors who performed the code work on the site held the ASME certificates of authorization, and these contractors were:

1) Wismer and Becker and 2) Pullman/Kellogg.

The inspector reviewed the following certificates of authorization issued for work at Diablo Canyon:

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Wismer and Becker Number PP 8187 PP 8188 N 655 N 656.

N 657

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N 658 N 659 Dates

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8/2/72-12/31/75 8/2/72-12/31/75 6/19/73-6/19/76 6/19/73-6/19/76

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6/19/73-6/19/76 Pressure piping.

"U" pressure vessel.

"NPT" Classes 1,

2 and 3 nuclear piping subassemblies.

'!NA" Classes 1,

2-,

3 and MC field

" installation of NU. Vessels, piping

< 'subassemblies, pumps and valves.

"NPT" Classes 1,

2 and 3 field fa'brication of NU. piping sub-

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NA Classes 1 p 2 p 3 and MC field installation of NU.

Vessels, piping

'subassemblies, pump/valves 37" maximum

., OD, 3" maximum thickness.

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"NPT" Classes 1,

2 and 3 field fabrication of NU.

Piping sub-assemblies 6" max OD, 1" maximum thickness.

N 1461-1 N 1462-1 N 1461-4 7/19/76-7/16/79 extended to 12/31/79 7/19/76-7/16/79 1/10/83-12/1/83

"NA" field installation of Classes 1,

2, and 3 vessels, pumps, valves, piping subassemblies and component supports.

"NPT" field fabrication of Classes 1,

2 and

MC components, supports and piping subassemblies.

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Dates T~e N 30A 3/2/72

"NPT" stamp for field fabrication.

N 392-2 12/18/72-12/18/75

"NPT" Classes 1, 2, 3 and MC field 12/18/72-completion fabrication of NU.

Parts, appurte-of contract.

nances, and piping subassemblies,

'Five extensions 72" maximum diameter to 10/14/86 N 393-2 12/18/72-12/18/75 12/18/72 to completion of contract.

Five extensions to 10/14/86

"NA" Classes 1, 2, 3 and MC field installation of NU. components, 72" maximum diameter.

The certificates and associated correspondence appeared to be in order.

This item is closed for 1Jnit 2.

The inspector conducted an exit meeting on January 17, 1986, with the Plant Manager, Plant Superintendent, and other members of the plant staff.

During this meeting, the inspector summarized the scope of the inspection activities and reviewed the inspection findings as described in this report.

The licensee acknowledged the concerns identified in the repor <<,(>> 4

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