ML20141N158

Insp Rept 50-354/86-11 on 860127-31.No Violation Identified. Major Areas Inspected:Action on Previous Insp Findings, Licensee Response to IE Bulletins & Reactor Pressure Vessel Internals Record Review

ML20141N158
Person / Time
Site:	Hope Creek
Issue date:	02/21/1986
From:	Mcbrearty R, Wiggins J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20141N152	List: ML20141N151 ML20141N158
References
50-354-86-11, IEB-80-07, IEB-80-13, IEB-80-7, NUDOCS 8603040427
Download: ML20141N158 (6)

See also: IR 05000354/1986011

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U.S. NUCLEAR REGULATORY COMMISSION

REGION I

Report No. 50-354/86-11

Docket No. 50-354

License No. CPPR-120 Priority -

Category B

Licensee: Public Service Electric & Gas Company

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Post Office Box 236

Hancocks Bridge, New Jersey 08038

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Facility Name: Hope Creek Generating Station, Unit 1

Inspection At: Hancocks Bridge, New Jersey

Inspection Conducted: January 27-31, 1986

Inspector: - O & A A O!rPd

R.A.McBrearty,ReactorEnginpr date

Approved by: [G.#'//#e/ 41- 't /'2 / N 6

J. T. Wiggins, Chief, Mat'erials & Processes date

Section, DRS

Inspection Summary: Inspection on January 27-31, 1986 (Report No.50-354/86-11).

Areas Inspected: Routine, unannounced inspection of licensee action on pre-

vious inspection findings; licensee response to IE Bulletins; RPV Internals

record review; Preservice Inspection (PSI) program review and data review.

The inspection involved 44 hours5.092593e-4 days <br />0.0122 hours <br />7.275132e-5 weeks <br />1.6742e-5 months <br /> onsite by one regional based inspector.

Results: No violations were identified.

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DETAILS

1. Persons Contacted -

Public Service Electric & Gas Company

• A. D. Barnabei, Principal Quality Assurance Engineer (QAE)

i R. Brandt, Nuclear Plant Systems Engineer

l *R. B. Donges, Lead QAE

l *J. T. Duffy, Site Engineering -

N. Dyck, Response Coordination Team Chairman

"M. Farschov, Manager-Power Ascension

C. Fuhrmeister, QAE

• A. E. Giardino, Manager-Station QA-Hope Creek

• R. T. Griffith, Principal QAE

L. Lake, ISI Engineer

H. Lowe, Senior Engineer-Nuclear QA

T. McLaughlin, QAE

• J. Nichols, Technical Manager

• R. S. Salveson, General Manager, HC0

B_echtel Engineering Corporation

"W. Goebel, QAE

• A. Indico, PSSUG

• C. Jaffee, PSSUG

• G. Moulton, Project, QAE

Southwest Research Institute (SWRI)

H. Diaz, NDE Level III

U.S. Nuclear Regulatory Commissio_n

• D. Allsopp, Resident Inspector

• R. Borchardt, Senior Resident Inspector

I *D. Florek, Lead Reactor Engineer

• C, Petrone, Lead Reactor Engineer

• Irdicates those present at the exit meeting on January 31, 1986.

2. Licensee Action on Previous Inspection Findings

(Closed) Unresolved Item (354/85-46-01): Evidence that an ultrasonic .

indicat'an was evaluated. Inspection Report No. 354/85-60 discusses  !

actions committed to by the licensee to resolve the subject item. Based i

on a lot size of 91 welds the licensee selected a sample of twenty welds

from various systems, pipe diameters and thicknesses. The inspector l

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reviewed the evaluations which were based on indication plots and reso-

lution sheets representing the sample welds and found that the welds were

acceptable.

Based on the above this item is considered closed.

(Closed) Unresolved Item (354/85-60-01): Ultrasonic indications plotted

from the wrong side of the weld. The sketch of elbow to pipe weld 1-88-28

VCA-013-4 on which the indication plots were done did not identify the

elbow side or the pipe side, nor was the direction of flow through the

pipe identified. The licensee provided additional information including

ultrasonic thickness measurements of the weld and base material on each

side of the weld which identified the direction of flow through the pipe.

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At the inspector's request the licensee provided a fabrication drawing,

NABC0 drawing NA1026-2 Revision I, which documented the inside diameter

dimensfor.s and wall thickness measurements of the pipe which was used to

fabricate the joint.

The inspector's review of the above documentation indicated that the

ultrasonic indications in weld 1-88-28 VCA-013-4 were correctly plotted

and evaluated.

Based on the above this item is considered closed.

(Closed) Unresolved Item (354/85-60-02): Ultrasonic indications plotted

using incorrect beam angle. Information supporting the plots and re plots

of the indications drawn by a SWRI Level III were provided by the licensee

to the inspector. In addition, the inspector interviewed licensee and

SWRI personnel. The inspector's review of the supporting documentation

and his discussions with the SWRI Level II indicated that the plots accu-

rately identified the location of the reflecters which produced the subject

ultrasonic indications.

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Pased on the abose this item is consideiea closed.

3. Follow-up on IE 3ulletins

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(Closed) IE Bulletin (80-BU-07): BWR Jet Pump Assembly Failure. The

Bulletin actions were addressed to bhp. licenses with Operating Licenses,

and are not applicable at this time to the Hope Creek facility. However,

The licensee committed in FSAR Section 3.9.5.1.2.1 to reduce, from 30 kips

to 25 kips, the pre-load on the hold-down beams in accordance with General

. Electric Company recommendations. Licensee document M9-IAP-102 Revi-

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sion 00, Attachment 2 addresses the actions required by the Bulletin and

states that implementation will be via the ISI long Term Plan, Section 1.

~ Further, the inspector noted that Standard Technical Specifications (STS)

contata the jet ptmp operability requirements described in the Bulletin

brJ that the STS would be used as a basis for the Hope Creek Technical

Specifications.

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l This completes the licensee's actions at this time regarding Bulletin *

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80-07,

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i (Closed) IE Bulletin (80-BU-13): Cracking in Core Spray Spargers.

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The Bulletin actions were addressed to ifcensees with Operating Licenses,

! and are not applicable at this tirre to the Hope Creek facility. However,

the licensee has responded to the Bulletin and has committed to the

j actions required by the Bulletin. The commitment is documented in

j M9-IAP-102 Revision 00, Attachment 2, and will be included in the In-

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service Inspection Long Term Plan.

] This completes the licensee's actions at this time regarding Bulletin

i 80-13.

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j 4. Preservice Inspection (PSI) Frogram  ;

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i The PSI program at Hope Creek was implemented by the Southwest Research I

( Institute (SWRI), the licensee's vendor. Original data generated during ,

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the performance of the examinations are maintained for the licensee by  ;

} SWRI at San Antonio, Texas, and copies of the data are kcpt by the licen-

j see on site. Discussions by the inspector with licen:,ee personnel regard-

! ing data storage and control indicated that the licensee will control PSI  ;

i data in the same way that it controls ISI data associated with the two [

] Salem facilities. This control is exerted by periodic licensee QA audits  ;

! of SWRI at San Antonio, and has proven to be an acceptable method of  :

control of ISI records. In response to the inspector's question the l

l licensee stated that the date of the next QA audit of SWRI has not yet t

been established. The inspector was advised that the last audit at San

Antonio, Texas, was performed tre 1984 and that these audits are done at  !

three year bitervals.

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No violations were identified.

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,SI Data Review t

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! The PSI Final Report listed welds which could not be completely examined

j in accordance with ASME Code Section XI requirement . The inspector

reviewed selected data to ascertain that tne examination limitations were l

properly documented and were, in fact, valid linitations. Data associated

with the following welds were included in the inspector's review:

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Rect-culation System pipe to pice wald 1-E3-28VCA-012-5

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• Recirculation System branch t;ohnection weld 1-08-28VCA-013-1BC1

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• RHP, value to flange weld 1-BC-6BA-003-21

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j * RHR pipe to reducer weld 1-BC-2 DBA-120-5 l

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• RHR Hest Exchanger "A" shell to flange weld RHX-W4

• Recirculation System pipe to safe-end weld 1-88-12VCA-014 B-5

Reactor Water Clean-up System weldolet to pipe weld 1-BB-4CCA-012-01

Reactor Pressure Vessel closure head to flange circumferential

weld RPV1-W20

The inspector attempted visual inspection to verify examination limita-

tions but was precluced by the presence of insulation on the pipes. Weld

contour sketches, ultrasonic examination data sheets, examination summary

record sheets and associated data included in the final report were used

by the inspector to make his determination of the validity of the exami-

nation limitations.

Based on the records the inspector found that the licitations are valid,

and that t'he related weld! were examined in accordance with Section XI

requirements to the greatest extent possible.

No violations were icentified.

6. Reactor Pressure Vesfel Internals - Record Reviqw

The inspec'or reviewed installation and surveillance records related to

the reactor pressare vessel and the reactor vessel internals to ascertain

that the associated work activities were done in accordance with

applicable requirements, that required surveillances were done on a

timely basis, and that the records were readily retrievable.

The reviewed records were associated with the core support plate and

the vessel shroud, included welding, NDE, dimensional checks, component

alignment and the removal of temporary attachments which were required

for the installation of the component. Maintenance Action Cards were

reviewed which documented CA/QC surveillances during the period from

Ncvember 27, 1978 when the reactor vessel was stored outside on Pad "0",

until March 1, 1985, the time Pre-Op testing started.

The records were readily retrievable and confirmed that the associated

work activities were done in accordance with applicable requirements and

that the periodic surveillances were performed at the required

frequency.

In addition to the above, the inspectcr revfesed nonconformance reports

to ascertain that ranconforming items were cocumented, and that proper

corrective action was taken.

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General Electric Company NCR #43 was related to core plate stud identi-

l fication, and NCR #14 was related to an arc strike and weld splatter on

the vessel shroud buttering.

The two NCRs clearly identified the nature and location of the non-

conforming condition, provided a proposed resolution, and were

l properly closed out after corrective action was taken.

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No violations were identified.

7. Exit Interview

The instector met with licensee representatives (denoted in paragraph 1)

at the conclusion of the inspection on January 31, 1986. The inspector

summarized the purpose and the scope of the inspection and the findings.

At no time during this inspection was written material provided by the

19specto" to the licensee.

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