ML20004D433

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IE Insp Repts 50-440/81-08 & 50-441/81-08,on 810401-30. Noncompliance Noted:Failure to Follow Specs for Installation of Reactor Vessel Internals
ML20004D433
Person / Time
Site: Perry  FirstEnergy icon.png
Issue date: 05/20/1981
From: Julie Hughes, Warnick R
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20004D430 List:
References
50-440-81-08, 50-440-81-8, 50-441-81-08, 50-441-81-8, NUDOCS 8106090393
Download: ML20004D433 (5)


See also: IR 05000440/1981008

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U.S. NUCLEAR REGULATORY COMMISSION

OFFICE OF INSPECTION AND ENFORCEMENT

REGION III

Report Nos: 50-440/81-08; 50-441/81-08

Docket Nos:

50-440; 50-441

License Nos.:

CPPR-148; CPPR-149

Licensee: Cleveland Electric Illuminating Company

P. G. Box 5000

Cleveland, OH 44101

Facility Name: Perry Nuclear Power Plant, Units 1 and 2

Inspection At: Perry Site, Perry, OH

Inspection Conducted: A il 1-30, 1981

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Inspector:

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Approved By:

R. F. Wrnick, Chief

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7/2(1/8/

Reactor Projects Section 2B

Inspection Summary

Inspection on April 1-30, 1981 (Report No. 50-440/81-08; 50-441/81-08)

Areas Inspected: Routine inspection by the IE Regional Resident Inspector of

. afety related construction activities, including followup on previously

identified unresolved items (Units 1 and 2); followup on 50.55(e) report of

fuel handling pool penetrations (Units 1 and 2); plant tours (independent

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inspection); observation of welding on electrical penetrations (Unit 1);

observation of installation of reactor vessel internals' (Unit 1); and ob-

servation of structure steel activities (Units 1 and 2).

This inspection

involved 195 inspector-hours onsite by one NRC inspector including 33

inspector-hours onsite during off-shifts.

Results: In the areas inspected, one apparent violation was identified

(failure to follow specifications for installation of reactor vessel inter-

nals - Paragraph 6.b.).

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DETAILS

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1.

Persons Contacted

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a.

CEI

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  • M. Edelman, Manag.r, Nuclear QA Department
  • G. Groscup, Manager, Nuclear Engineering Department

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J. K3ine, General Supervising Engineer, Construction

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P. Martin, General Supervising Engineer, PQS

G. Leidich, CQS QA Supervisor

K. Combs, CQS Engineering Aide

S. Tulk, CQS Lead Electrical Quality Engineer

T. Thompson, CQS Electrical Quality Engineer

E. Christiansen, Nuclear Electrical Engineer

  • J. Bellack, General Supervisor Engineer, Administration & Special Products

b.

Other Contractors Personnel

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J. Gilstrap, CQS, Mechanical Quality Engineer (GAI)

J. Anulies, Site QA Manager (PBI)

C. Burnett, Engineer Quality Manager (Kelley Steel)

C. Hart, VA/QC Manager (LKC)

D. Hess, QA Manager (GE ISEE)

J. Bucka, QA Engineering (GE NEBG)

The inspector also contacted and interviewed ather licensee and contractor

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personnel during this reporting period.

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  • Denotes those attending at least or.e of the exit meetings.

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2.

Licensee Action on Previous Inspection Findings

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(Closed) Unresolved Item (440/81-02-01; 441/81-02-01):

CEI, unable to pro-

duce seismic qualification data addressing the use of spade lugs for termi-

nation and connections in General Electric (GE) supplied termination cabinets

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(PGCC) in the control room.

The RI reviewed GE letter dated March 30, 1981

to the licensee, subject " Qualification of Panels with Lock on Fork Spade

Lugs".

GE stated that a survey of seismic qualifications records has shown

that spade lugs were used on Limerick Panel H12-P603 and successfully com-

pleted seismic qualification testing. The inspector did not review the

seisaic report DRF #H12-10.

The RI observed several spade lugs located in

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the t rmination cabinets and determined that they were the same as GE's

spade lug drawing number 225A4895, revision 8.

The RI has no further

questions on this matter and this item is closed.

3.

Licensee Action on Other Items - Units 1 and 2

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(Open) 10CFR50.55(e) Report, Subject: " Deficiency concerning the degradation

of the G-41 System, fuel handling pool yenetration piping." The RI observed

the replac: ment of the fuel pool penetration number 8 by Newport News In-

dustrial Corporation (NNIC) in accordance with nonconforming report (NR)

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  1. 53-204, revision 6.

The inspector witnessed the fit-up of the replacement

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backing ring, replacement liner, and leak chase. Welding was performed

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in accordance with NNIC Weld instruction 946-N-WOO 1.

The RI witnessed

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Pullman Power Products (PPP) in-process repair of penetration number 12.

The inspector determined the following; work was conducted in accordance

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with PPP welding procedures; proper welding materials were used; field

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process sheet was current; and liquid penetrant inspection was conducted

in accordance with PPP procedure IX-PT-1.

4.

Functional or Program Areas Inspected - Units 1 and 2 (Independent Inspection)

One or more plant areas were toured several times during this reporting

period to observe general construction practices.

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During the week of April 7-10 of this reporting period, the RI observed

Region III' electrical inspector's activities on Units 1 and 2.

Summary

and findings are contained in IE Inspection Report 81-07.

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Three tours were made on off shift.

No items of noncompliance or deviations were identified.

5.

Observation of Electrical Penetrations Work and Work Activities - Unit 1

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The inspector observed in-process work activities including welding of

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safety related electrical penetrations located in the containment.

The inspector observed the in-process fit-up and welding of

a.

electrical penetration equipment numbers 1R725012, 1R725013 and

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1R725007 in accordance with PPP welding procedure WPS-IT-12A,

Westinghouse drawing no. E-40047, ISO-1R72-12, revision A.

b.

It was determined that (1) work was conducted in accordance with

welding procedures and drawings; (2) proper welding materials were

used; (3) the work area was free of weld rod stubs; and (4) physical

appearance was acceptable.

No items of noncomplian'ce or deviations were identified.

6.

Observation of Installation of Reactor Internals - Unit 1

During this reporting period the inspector observed the installation of

the reactor internals.

a.

On April 10, 1981 the inspector witnessed the installation of the

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shroud assembly (Il-B13-01) in acccrdance with General Electric (GE)

layout drawing no. E-015-04A, drawing no. 8-370-0, revision 3 and

traveler no. T1-B13-01.

Prior to the installation of the shroud

assembly, the reacter vessel war vacuum cleaned. However, when the

vacuum cleaner was turned off, the hose was still inside the vessel

and dirt, duat and small foreign particles fell back down into the

vessel. The inspector is unable to determine at this time if the

reactor vessel is still in a class "B" cleanliness condition in

accordance with GE specification 21A2045, revision 2.

This item is

considered an unresolved item.

(440/81-08-01)

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b.

On April 12, 1981 the installatien of the steam dryer / separator

(1B13-D005) into the reactor vessel was being conducted during ad-

verse weather conditions. GE specification 22A4671 paragraph 3.10.1

states in part "A protective cover shall be built over the top of the

vessel. This cover shall not be removed for installation of internal

parts unless the weather forecasts indicate reasonable assurance that

rain or storms are not imminent and that there will be time to replace

the cover." The inspector questioned the licensee on this subject.

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The licensee notified the inspector that nonconforming reports (NR)

GE38-194 and GE38-199 were issued on this matter. Also, the Nuclear

Quality Assurance Department issued an Action Request ( AR) #297.

During an inspection of the internals on April 16, 1981, the RI and

GE QC personnel found that the internals had water (approximately

1 gallon) still standing on them. This condition represents an item

of noncompliance as identified in Appendix A.(440/81-08-02)

7.

Observation of Structure Steel Work and Work Activities - Units 1 and 2

The inspector observed work activities including welding, receipt in-

spection and storage of structure s teel,

The inspector observed receipt inspection of safety related structure

a.

steel and determined that procedural requirements had been met and

that inspections verify acceptability in accordance with Pittsburg

Bridge Iron (PBI) specification no. 85 and Quality Assurance Program,

Section 10.

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b.

Tour of the storage area was made by the inspector to determine that

control, marking, protection and segregation were in accordance with

PBI Quality Assurance Program, Section 13.

The inspector observed partially completed and completed columns Y5,

c.

Y6, Y7 and Y10 located at the 578 ft. elevation in reactor buildings.

The inspector determined that installation was in accordance with

the lay-out drawings D-561-036 and D-561-038.

Welding was being per-

formed by qualified welders anu PBI welding procedure specification

SMA-14 for joint ?: sign, weld rod issue slip was correct in accordance

with PBI Quality Assurance Program, Section '9, Paragraph F.3.

The

inspector determined that the fit-up/ alignment was within the toler-

ances of the drawings.

NOTE: During the inspector's observation of the welding activities,

the inspector asked the welders (4) how they determined the

pre-heat temperature (2250 F.).

The welders stated that they

were issued temp-sticks by the Quality Control Section, but

were unable to produce them due to various reasons. Prior to

the inspector leaving the work aret, PBI QC section reissued

new temp-sticks to each welder / fitter. PBI also issued a

Corrective Action Notice (CAN)

No. 4-81-1 to construction

immediately. A training session was held the same day instruc-

ting welders / fitters to use temp-sticks for pre-heat welding.

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d.

The inspector reviewed PBI ultrasonic examination test reports nos.

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UT-34-77-81-47U, UT-34-77-81-48U, UT-34-77-81-48SB and UT-34-77-81-49U

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for the aforementioned column welds. Test reports appear to be in

accordance with PBI procedure for ultrasonic examination, UT-NIC-059

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revision 4.

No items of noncompliance or deviations were identified.

Unresolved Items

Unresolved items are matters about which more information is required in order

to detemine whether they are acceptable items, items of noncompliance, or de-

viations. Unresolved items disclosed during this inspection are discussed in

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Paragraph 6.a.

Exit Meetings

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The inspector met with licensee representatives (denoted in Persons Contacted)

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on April 3, 10, 17 and 24, 1981. The inspector summarized the scope and findings

of the inspections perfomed.

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