IR 05000354/1986019
| ML20203K754 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 04/08/1986 |
| From: | Gregg H, Wiggins J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20203K748 | List: |
| References | |
| 50-354-86-19, NUDOCS 8605010030 | |
| Download: ML20203K754 (5) | |
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U.S. NUCLEAR REGULATORY COMMISSION
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REGION I
Report No.
50-354/86-19 Docket No.
50-354 License No.
CPPR-120 Priority Category B
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Licensee:
Public Service Electric & Gas Company Post Office Box 236 Hancocks, Bridge, New Jersey 08038 Facility Name: Hope Creek Generating Station
Inspection At: Hancocks Bridge, New Jersey
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Inspection Conducted: March 3-7, 1986
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7/ff, Inspector
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,,<f H.Greig, Leaf}eactorEngineer date
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Approved by:
W 8[h I
JCAI ggins,(9hipf, Material and Processes date
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Section-DRS Inspection Summary:
Inspec'. ion on March 3-7, 1986, Report No. 50-354/86-19.
Areas Inspected: Routine unannounced inspection to review licensee's activi-ties related to previously identified open items.
Results: No violations were identified.
354 PDR
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DETAILS 1.
Persons Contacted 1.1 Public Service Electric & Gas Company
- G. Daves, Sr. Operations Technical Supervisor
- R. Griffiths, Principal QA Engineer M. Maradeo, Lead QA Engineer J. Nichols, Technical Manager J. Ranalli, Sr. Staff Engineer C. Smith, Lead Mechanical Engineer
- C. Vondra, Operating Engineer 1.2 Bechtel Power Corporation
- W. Goebel, 0A Engineer D. Graham, Plant Design Supervisor J. Iqbol, Mechanical Engineer 1.3 U.S. Nuclear Regulatory Commission
- 0. Allsopp, Resident Inspector 2.0 Facility Tour The inspector observed work activities in progress, completed work and plant status in several areas during a general inspection of the Hope Creek facility. The inspector examined work items for obvious defects or noncompliance with NRC requirements or licensee commitments.
Parti-cular note was taken regarding the presence of quality control inspection personnel and indications of quality control activities through visual evidence such as inspection records, turnover tags, material identifi-cation, nonconformance and acceptance tags.
No violations were identified.
3.0 Licensee's Activities Related To previously Identified Items The inspector reviewed the licensee's responses and corrective actions taken to complete the close-out of the following previously identified items.
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3.1 (Closed) Unresolved Item No. 86-13-01 relating to lack of production test records for Pacific Scientific Company (PSA)
mechanical snubbers ar.d inability to verify that production tests were performed and met vendors acceptance criteria.
The inspector reviewed the letter dated February 14, 1986 from ITT Grinnell Corporation, Warren Ohio, the supplier of PSA snubbers.
The letter stated that:
ITT Grinnel has on file the performance reports for each PSA
mechanical snubber supplied under P0-10855-P-401(Q)
The documentation is available for the licensee's use and
inspection.
The documentation certifies tests have been completed for each
snubber and includes visual examination for workmanship, dimen-i sions, and final functional test results of break-away friction, lost motion and acceleration.
Test results comply with specification P0-10855-P-401(Q),
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section 7.5.5.
The inspector performed a walkdown in the drywell. The nameplate i
data for several snubbers were recorded and documentation was reviewed to verify that the installed snubbers correlate with the P0 snubbers.
The record system to track snubbers through their hanger or serial number was cumbersome; however, data was able to be obtained.
The licensee has addressed the concerns of this unresolved item.
This item is closed.
3.2 (Closed) Unresolved Item No. 85-58-02 relating to the stress limits for emergency and faulted conditions used in the Bechtel Specification No.10855-M-069(Q) for the Safety Auxiliary Cooling System (SACS) Heat Exchanger component supports.
The inspector reviewed the M-069(Q) specification and verified that the emergency condition stress limits were correctly revised to i
primary membrane og s 1.2S; primary membrane and bending oi + o s 1.85 n
The inspector reviewed the 1977 edition and addenda W76 of the ASME Code Section NF and determined that the emergency condition and faulted condition stress limits in the Bechtel specification M-069(Q)
are in agreement with the ASME requirements.
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Emergency Condition stress limits of the Bechtels specification are in agreement with ASME subarticle NF-3321.2 Level C service limits of:
primary membrane o s 1.2S; s
primary membrane + be., ding oi + a2 s 1.8S.
Faulted Condition stress limits of the Bechtel specification are in agreement with ASME subarticle NF-3321.2(d) Level D service limits of:
primary membrane o s lesser of 1.5S or 0.4 Su; r
primary membrane + bending oi + og s lesser of 2.25 S or 0.6 Su.
This item is closed.
3.3 (Closed) Construction Deficiency 85-00-10, relating to problems and repairs to Anchor Darling swing check valves.
This construction deficiency was initially closed in IR 85-61 after completion of repair to correct problem of missing lock welds at the hinge pin setscrew and disc nut pin.
Subsequent to this repair and the item being closed, the licensee was advised by the vendor (Anchor Darling) of another problem.
The new problem related to missing lock welds at two locations:
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The hinge support capscrews to the hinge, and 2)
The Hinge support to the bonnet.
Therefore, the item was reopened.
During the inspection, all sixteen valves were inspected and eight were miss.ing lock welds of the hinge suppcrt capscrew to the hinge support.
Further, it was found that the prior rework of the hinge pin set screw was not effective in locking the hinge pin to the hinge support.
The inspector reviewed the licensee's work order and PSE&G Field Directive PSE-FO-M-015 for repairs to be made. The irspector deter-mined that Icck weld of the hinge support capscrews were made on the eight valves. Additionally, the inspector determined that all sixteen valves were reworked in accordance with the PSE&G FD-015 which required drilling into the hinge pin to form a recess for the set screw, torquing of the set screw, and staking of the hinge support at the set screw location.
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4 The inspector encountered some difficulty in locating the records for retest after the maintenance.
In response, the licensee issued work orders to perform functional tests on all the repaired valves, and the inspector verified each of the work orders. Additionally, the licensee's staff committed to completion of the testing prior to fuel load.
The inspector concluded that the apparent absence of functional test records, in this instance, was not significant because the repair-technique implemented to address the CDR was appropriate.
The inspector had no further questions.
This item is closed.
4.0 Exit Meeting The inspector met with the licensee's representative (identified in paragraph 1.0) at the conclusion of the inspection on March 7, 1986, to summarize the findings of this inspection.
The NRC Resident Inspector, D. Allsopp, was also in attendance.
During this inspection, the inspector did not provide any written material to the licensee.