IR 05000354/1979007
| ML19257C866 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 10/21/1979 |
| From: | Bateman W, Mcgaughy R, Narrow L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19257C836 | List: |
| References | |
| 50-354-79-07, 50-354-79-7, 50-355-79-07, 50-355-79-7, NUDOCS 8001300631 | |
| Download: ML19257C866 (7) | |
Text
.
.
U. S. N'JCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION I
50-354/79-07 Report No.
50-355/79-07 50-354 Docket No.
50-355 CPPR-120 License tio.
CPPR-121 Priority Category A
--
Licensee:
Public Service Electric & Gas Company 80 Park Place Newark, New Jersey 07101 Facility Name:
Hope Creek Generating Station, Units 1 & 2 Inspection At:
Newark, New Jersey and Hancocks Bridge, New Jersey Inspection Conduc d:
September 25-27, 1979 Inspectors:
pf,f /p G//
/8!/f/77 C. ' Narrow ~, Reactor Inspector
/date
,fAr-ICbli h'7 A L-W. H. Bateman, Reactor Inspector
' date date Approved by:
///'L/////hp
/P/7/
R. W. McGaugh @ ief, Projects Section
~' ddt'e /
Inspection Summary:
Inspection on September 25-27, 1979 (Combined Report No.s 50-354/79-07; 50-355/79-07)
Areas Inspect _ed:
Routine unannounced inspection by regional based inspectors, which commenced on September 25, 1979 at licensee's corporate headquarters in Newark, New Jersey, of licensee action on Bulletins and Circulars.
The inspec-tion continued at the site on September 26 and 27, 1979 and included review of ASME Certificates of Authorization and status of outstanding items.
The inspec-tion involved 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> at licensee's corporate headquarters and 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> on site by two NRC regional based inspectors.
Results:
Of the areas inspected one item of noncompliance was identified (infraction-failure to follow procedures for timely resolution of potentially nonconforming items paragraph 3.)
1833 190-
'
Region I Form 167 8001300 O /
(August t979)
.
.
DETAILS 1.
Persons Contacted Public Service Electric and Gas Company R. Evans, Principal Engineer, QA
- A. E. Giardino, Project QA Engineer
- L. Jankowski, Site QA Engineer
- P. J. Kudless, Principal Construction Engineer F. Omohundro, Principal Engineer, QA E. Schwalje, QA Manager
- A. C. Smith, Project Construction Manager Bechtel Power Corporation (Bechtel)
R. Baldwin, QA Engineer
- R. Hanks, Project QC Engineer
- W. Hindle, Project Field Engineer W. Langdon, Mechanical Engineer R. McKinnon, Assistant Project Field Engineer C. Rogers, Lead Mechanical Engineer
- L. E. Rosetta, Field Construction Manager W. Woodman, QC Engineer Pittsburgh-Des Moines Steel Co. (PDM)
M. Steiger, QA Manager Schneider, Inc. (Schneider)
W. Goebel, Site QA Manager
- Denotes those present at the exit interview.
2.
Plant Tour (Units 1 and 2)
A tour of the site was made to observe the status of work and construc-tion activities in progress.
The inspectors examined work items for any obvious defects or noncompliances with regulatory requirements or license conditions.
Areas observed included:
placement of rebar for containment building floor at elevation 102'; completed piping and structural weld-ing in the pressure suppression chamber; placement and compaction of backfill; maintenance activities on installed components; conduit and cable tray installation; and structural steel grouting at elevation 100'.
No items of noncompliance were identified.
.
1833 191
.
.
3.
Resolution of Maintenance Inspection Punchlist Items The Bechtel Project Construction QC Engineer (PCQCE) is responsible for keeping maintenance records current.
Should maintenance activities require field engineering action for resolution, the PCQCE lists these potentially nonconforming items on a log called the " Maintenance Inspection Punchlist."
On a weekly basis, in accordance with the requirements of paragraph 6.4.6 of Bechtel Specific Work Plan / Procedure SWP/P-14, Rev. 4, the PCQCE updates this punchlist and sends it to the Resident Field Engineer (RFE) request-ing evaluation and corrective action. The RFE, in turn, is required as stated in paragraph 6.2.10 of SWP/P-14, to respond to the PCQCE on a weekly basis stating corrective action to be taken and estimated comple-tion dates for resolution of new punchlist items and revised dates for any remaining punchlist items.
Contrary to this established procedure, the RFE had not responded to the PCQCE's weekly request for corrective action since the week of July 10, 1979.
During this time four potentially nonconforming items had been added to the punchlist and no action had been taken by the RFE to clear them. This is an item of noncompliance relative to Criterion V of Appendix B of 10 CFR 50.
(354/79-07-01; 355/79-07-01)
4.
Review of Circulars Section 14 of the licensee's Engineering Department Organization and Design Procedure entitled " Review of NRC Bulletins, Circulars and Nuclear Power Experience Reports" had been revised on May 15, 1978.
The inspector reviewed the portion of this section which is concerned with review of circulars as well as a random selection of Form QAF 44's which provide the status and projected dates for review of circulars as well as responsible personnel.
The inspector observed that projected dates for review of a number of circulars had been established on Form QAF 44's but no further action had been documented.
In one case, circular 78-15, the review had been completed; in others completion of the work was as much as six months overdue.
This item is unresolved pending licensee action to update the outstanding QAF 44 forms.
(354/79-07-02; 355/79-07-02)
5.
Storage Requirement - RHR and Core Spray Pumps General Electric Company Procedure No. 22A2724, " Equipment Storage Require-ments" establishes a requirement for inside unheated storage with conden-sate protection for the RHR and core spray pumps and that vendor supplied instructions will be followed.
The vendor's (Ingersoll-Rand) instructions are contained in Procedure No. CQCP-1088 (GE No. V2993-212-3) which pro-vides requirements for long and short term storage for various pumps including RHR and Core Spray pumps.
1833 192
.
.
The licensee had heat traced this equipment during storage in the ware-house.
However, since installation of the discharge heads and shells for the RHR and core spray pumps no means of condensate protection has been provided.
Bechtel Field Engineering stated that use of a rust inhibitor was under consideration and awaiting GE approval.
This item is unresolved pending review by an NRC inspector of the method of providing condensate protection for this equipment while it is stored in place.
(354/79-07-03)
6.
Status of Bulletins and Circulars The inspector reviewed records concerning licensee action on NRC issued Bulletins and Circulars and discussed these actions and records with licensee personnel responsible for processing Bulletins and Circulars.
The Bulletins listed below were closed based on reviews by Bechtel and/or the NSSS which showed that the equipment in question had not been ured and instructions had been issued to assure that it would not be used for these plants.
Bulletin Numberc Description 77-01 Pneumatic Time Delay Relay Set Point Drift
.
78-05 Malfunctioning of Circuit Breaker. Auxiliary
.
Contact Mechanism - GE Model CR105X 78-06 Defective Cutler-Hammer Type M Relays with DC Coils
.
78-10 Hydraulic Shock Suppressor Accumulator Spring Coils
.
79-03 Longitudinal Weld Defects in ASME SA-312 Type
.
304 Stainless Steel Pipe Spools Manufactured by Youngstown Welding and Engineering Company 79-04 Incorrect Weights for Swing Check Valves
.
Manufactured by Velan Engineering Corporation 79-09 Failures of GE Type AK-2 Type Circuit Breaker
.
in Safety Related Systems 79-11 Faulty Overcurrent Trip Device in Circuit Breakers
.
for Engineered Safety Systems The Bulletins listed below were closed either because they were not appli-cable or they had been sent to this plant for information only and the information had been disseminated through licensee and contractor channels.
i833 193'-
.
.
.
Bulletin Number Description 78-14 Deterioration of Buna-N Components In ASCO
.
Solenoids 79-05 & SA Nuclear Incident at Three Mile Island
.
.
79-06,79-06A, Review of Operational Errors and System Misalign-79-06A, Rev. 1 ments Identified During the Three Mile Incident and 79-06B 79-08 Events Relevant to Boiling Water Power Reactors
.
Identified During Three Mile Island Incident 79-10 Requalification Training Program Statistics
.
The circulars listed below are closed because the conditions described are not applicable to this site or because the records show that corre-tive action has been initiated or completed.
Circular Number Description 77-11 Leakage of Containment Isolation Valves with
-
.
Resilient Seats 78-02 Proper Lubricating Oil for Terry Turbines
.
78-03 Packaging Greater Than Type A Quantities of Low
.
Specific Activity Radioactive Material for Transport 78-04
~
Installation Errors That Could Prevent Closing
.
of Fire Doors 78-06 Potential Common Mode Flooding of ECCS Equipment
.
Rooms at BWR Facilities 78-07 Damaged Components on a Bergen-Paterson Series
.
25000 Hydraulic Test Stand 78-09 Arcing of General Electric Company NEMA Size 2
.
Contactors 78-12 HPCI Turbine Control Valve Lift Rod Bending
.
78-13 Inoperability of Multiple Service Water Pumps
.
78-14 HPCI Turbine Reversing Chamber Hold Down Bolting
.
'
78-15 Tilting disk Check Valves Fail to Close with
.
Gravity in Vertical Position
Obb
.
.
Circular Numog Description 78-18 UL Fire Test
.
79-04 Loose Locking Nut on Limitorque Valve Operators
.
79-12 Potential Diesel Generator Turbocharger Problem
.
7.
Licensee Action on Previous Inspection Findings (Closed) Unresolved Item (354/79-02-03):
Fillet welds of angular supports.
Bechtel letter, BLP 8309, dated June 27, 1979 states that pipe support installation specifications are being revised and pipe details will specify groove welds where the angle between members exceeds 135 degrees and no fillet welds will be specified for angles less than 60 degrees.
Since the fillet wetds previously identified had not been inspected by Field QC, they will be inspected to the above requirements.
(Closed) Unresolved Item (355/79-04-01):
Excessive bleeding Concrete Mix A-BMCB-C-1.
Engineering has reviewed the mix design and inspected mix.
Bleeding was due to increase in amount of water used in order to obtain a higher slump for placement in congested areas.
Mix is considered acce table by engineering (Bechtel letter BLP #38,865 dated August 14, 1979.
(Closed) Unresolved Item (354/79-05-02; 355/79-05-02):
Procedural require-ments for control of Maintenance Inspection Punchlist items.
Specific Work Plan / Procedure SWP/P-14, (Rev. 4) and QCI S-2.00, Rev. 5 require that Field QC will maintain a sequential log of potentially nonconforming items and send copies of this log to Project Field Engineering who will initiate corrective action, provide estimated completion date to FQC and will up-date status of such action weekly.
(Closed) Unresolved Item (354/79-05-03):
Excessive weld gap at fitup.
At the time this observation was made PDM QC had not inspected fit-up of the joints.
CAR's No. 22489 and 22490 and FCA's No. 44 and 46 show build up of weld seam, nondestructive testing, and visual inspection of these weld joints prior to release for welding.
(Closed) Unresolved Item (354/79-05-04; 355/79-05-03):
Inspection attri-butes for visual inspection of completed welds.
QCI C-2.10 has been revised to define inspection requirements in accordance with specifications C-126 and C-130.
(Closed) Unresolved Item (354/79-05-05; 355/79-05-05):
Humidity control of E7018 welding electrodes. Bechtel" report " Qualification of an Alter-native Electrode Control Program for AWS D1.l' provides results of tests of E7018 electrodes exposed to high humidity conditions including expo -
sure to 100% humidity for periods of 15 and 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br />.
-
1833 195
'
8.
Verification of Compliance with ASME Certification System Requirements The inspector verified that the licensee has an established organization for construction of Hope Creek Generating Station that satisits ASME Section III, Article NA-3000 requirements.
The valid Certificates of Authorization t'or work being performed are as follows:
Certificate Certificate Type of Expiration Holder Ntimber Authorization Date Public Service N-2178 (Unit 1)
N-3 Form 10/2/81 Electric & Gas N-2179 (Unit 2)
N-3 Form 10/2/81 Pittsburgh-Des-N-1492-2 N
1/17/81 Moines Steel Co.
N-1493-2 NA 1/27/81 Schneider, Inc.
N-1824 NA
"
N-1825 NPT
Bechtel Power N-1917 NPT
Corporation N-1915 N
N-1916 NA
- Sr'... eider had an ASME site survey on 8/14-8/15/79 to extend their Certi-ficate of Authorization to the Hope Creek site.
- Bechtel intends to request an ASME site survey 6/80 to extend their Certificates of Authorization to Hope Creek.
9.
Limitorque Operators on Valves Supplied by Anchor Darling In paragraph 15. of Combined Inspection Report 50-354/79-05 and 50-355/
79-05, it was erroneously stated, "...that the valves to be used inside containment do not have type "H" insulation." The correct statement is that the valves to be used inside containment do have type "H" insulation.
10.
Unresolved Items Unresolved items are matters about which more information is required in order to ascertain whether they are ccceptable items, or items of noncom-pliance.
Unresolved items identified during the inspection are discussed in paragraphs 4 and 5.
11.
Exit Interview The inspector met with licensee representatives (denoted in paragraph 1)
at the conclusion of the inspection on September 27, 1979.
The inspector summarized the scope and findings of the inspection.
.g33 196