ML20141N158
| 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: |
| 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
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Category
B
Licensee: Public Service Electric & Gas Company
_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
A O!rPd
Inspector:
O
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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
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Persons Contacted
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Public Service Electric & Gas Company
- A. D. Barnabei, Principal Quality Assurance Engineer (QAE)
R. Brandt, Nuclear Plant Systems Engineer
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- R. B. Donges, Lead QAE
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- J. T. Duffy, Site Engineering
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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
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- 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
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indicat'an was evaluated.
Inspection Report No. 354/85-60 discusses
actions committed to by the licensee to resolve the subject item.
Based
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on a lot size of 91 welds the licensee selected a sample of twenty welds
from various systems, pipe diameters and thicknesses.
The inspector
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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.
At the inspector's request the licensee provided a fabrication drawing,
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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.
Pased on the abose this item is consideiea closed.
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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
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Electric Company recommendations.
Licensee document M9-IAP-102 Revi-
sion 00, Attachment 2 addresses the actions required by the Bulletin and
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states that implementation will be via the ISI long Term Plan, Section 1.
Further, the inspector noted that Standard Technical Specifications (STS)
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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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This completes the licensee's actions at this time regarding Bulletin
80-07,
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(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,
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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
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actions required by the Bulletin. The commitment is documented in
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M9-IAP-102 Revision 00, Attachment 2, and will be included in the In-
service Inspection Long Term Plan.
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This completes the licensee's actions at this time regarding Bulletin
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80-13.
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4.
Preservice Inspection (PSI) Frogram
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The PSI program at Hope Creek was implemented by the Southwest Research
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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
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SWRI at San Antonio, Texas, and copies of the data are kcpt by the licen-
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see on site.
Discussions by the inspector with licen:,ee personnel regard-
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ing data storage and control indicated that the licensee will control PSI
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data in the same way that it controls ISI data associated with the two
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Salem facilities. This control is exerted by periodic licensee QA audits
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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
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licensee stated that the date of the next QA audit of SWRI has not yet
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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
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three year bitervals.
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No violations were identified.
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5.
,SI Data Review
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The PSI Final Report listed welds which could not be completely examined
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in accordance with ASME Code Section XI requirement .
The inspector
reviewed selected data to ascertain that tne examination limitations were
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properly documented and were, in fact, valid linitations. Data associated
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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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RHR pipe to reducer weld 1-BC-2 DBA-120-5
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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-
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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
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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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