IR 05000363/1979007
| ML19254E068 | |
| Person / Time | |
|---|---|
| Site: | 05000363 |
| Issue date: | 08/22/1979 |
| From: | Mcgaughy R, Narrow L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19254E059 | List: |
| References | |
| 50-363-79-07, 50-363-79-7, NUDOCS 7910310038 | |
| Download: ML19254E068 (9) | |
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT Region I Report No. 50-363/79-07 Docket No. 50-363 License No. CF.R-96 Priority:
Category:
A
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Licensee:
Jersey Central Power & Light Company 260 Cherry H;11 Road Pursippany, New Jersey 07054 Facility Name:
Forked Oiver Nuclear Station, Unit 1 Inspection at:
Forked River, New Jersey Inspection conducted:
Jun 25-27, 1}79 b//7/7 Inspectors:
1A.,.
/
L. Narrow, Reactor In~spector date si'gne'd Approved by:
M ///
fha /77 t
R. W. McGaughyf ef, Construction d6te signed Project Section, C & ES Branch Inspection Summary:
Inspection on June 25-27, 1979 (Report No. 50-363/79-07)
Areas Inspected:
Routine, announced inspection by a regional based inspector of the QA program for storage and maintenance of equipment, materials, and structures during suspension of construction; and the status of outstanding items.
The inspection involved 23 hours2.662037e-4 days <br />0.00639 hours <br />3.80291e-5 weeks <br />8.7515e-6 months <br /> on ::ite by one regional based inspector.
Results:
One item of noncompliance was identified in the one area inspected.
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DETAILS
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Persons Contacted
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Jersey Central Power & Light Company W. T. Murray, Area Surveying Supervisor General Public Utilities Service Corporation (GPU)
- D. Callahan, FRNS Environmental Scientist
- R.
Fenti, Senior Site Auditor
- J. Griest, Project Construction Manager
- R. E. Hettler, Preventive Maintenance Engineer
- T..Hreczuch, Engineer
- G.
Porr, Project Site Administrator D. Rees, Acting Project Manager
- S. A. Salcwitz. Senior Site QA Representative
- M. J. Stromberg, Chief QA Auditor Stone and Webster Engineering Corporation (S&W)
- D. T. Bodkin, Senior Site Representative
- Denotes those present at the exit interview.
2.
Plant Tour The inspector made a tour of the site to observe activities in progress for preservation of installed structural materials; the status of laydown and storage areas; and measures taken to mini-mize soil erosion.
No items of noncompliance were identified.
3.
Storage and Maintenance Records The inspector reviewed Equipment Storage History Cards (ESHC's)
for the period January, 1979, to date.
The cards werc examined to determine conformance to the established requirements for long term storage, for records of periodic maintenance and for records of surveillance by QA.
The ESHC's for the following items of equipment were examined by the inspector:
No. CH-P-3A Boric Acid Makeup Pump and Motor ESHC No. 1750 No. CH-P-3B Boric Acid Makeup Pump and Motor ESHC No. 1751 1744 035
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- 3-No. CH-P-4A Hold-up Pump and Motor ESHC No. 1752 No. CH-P-48 Hold-up Pump and Motor ESHC No. 1753 No. CH-P-5A Reactor Drain Tank Dump and Motor ESHC No. 1754 Na. CH-P-5B Reactor Drain Tank Pump and Mctor ESHC No. 1755 No. CH-P-6A Equipment Drain Tank Pump and i% tor ESHC No. 1756
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No. CH-P-6B Equipment Drain Tank Pump and Moter ESHC No. 1757 S/N E-SPD-165-120-1 Surveillance Capsule Retrieval Tool ESHC No. 1958 The inspector noted that these ESHC's had not been reviewed and approved by GPUSC-QA and also that surveillance inspection of these items and other equipment had not been conducted since late March, 1979.
Paragraph 6.1.2 of Field Shutdown Procedure, FSP l-05 states, in part, "The original ESHC will be forwarded to GPUSC for review and approval.
GPU... shall signify approval by signcture and date at the bottom of the card."
Paragraph 5.1 of GPUSC QC Procedure FR-13-01, Rev. O, states, in part, that GPUSC QA is responsible for " Performing and documenting surveillance inspections of preventive service and storage program"
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and " Review and approval of storage and servicing instructions.
..
This item is considered to be in noncompliance with 10 CFR 50, Appendix 8, Criterion V.
(363/79-07-01.)
4.
Long Term Storage and Maintenance 6rocedures The inspector reviewed the licensee's long term storage and main-tenance program including the field shutdown procedures listed below:
a.
FSP-1-01, Rev. O, Receiving, Storage, Handling and Control of Furnished Equipment This procedure had w t been approved.
It referenced the following GPUSC and S&W procedures:
o SW/FR-1/FCP 7-01 Receiving, Storage, and Handl11g of 0FE o
FR-7-01 Receiving Inspection o
FR-7-02 Receiving, Storage, Handling, Control and Issue of 0FE o
FR-13-01 Preventive Services to Stored Equipment o
FR-14-01 Inspection and Tast Status Indicator;,.
b.
FSP-1-02, Rev. O, Notification of Fire Protection /or Dewatering System Failure y A 0%
-4-c.
FSP-1-03, Rev. O, Control of Manufacturer's Representatives d.
FSP-1-04, Rev. O, Building Settlement Monitoring Program e.
FSP-1-05, Rev. O, Preventative Services This procedure referenced GPUSC QC Procedure FR-1-15-01, Control of Nonconformances f.
FSP-1-08, Rev. O, Notification of Fire at Site and Response by Site Protection Staff g.
FSP-1-09, Maintenance of Quality Assurance Record Vault and Computer Room h.
FSP-1-10, Site Environmental Control Program i.
FSP-1-11, Disposition and Accounting of Scrap, Surplus Material and Equipment J.
FSP-1-12, Venting of Air Building k.
FSP-1-14, Calibration.
The index of shutdown procedures also listed Procedure FSP-1-15, Reporting of Serious Incidents.
However, the inspector was informed that this procedure had not been prepar-ed since it had been decided that serious incidents would be reported in accordance with standard GPUSC Procedures:
o S & L-1, Rev. 1, " Evaluating Reportability of Deficiencies to the United States Nuclear Regulatory Commission Under 10 CFR 50.55(e) and 10 CFR 21" and o
SPP C-3.01 " Reporting of Significant Deficiencies to the USNRC."
The shutdown procedures which together with certain previously reviewed GPUSC QC procedures do not provide a complete and specific long term storage and maintenance program.
As examples:
o There is no provision for inspection of substructure protection.
o FSP-1-09 requires that the QA records would be maintained to prevent damage to records, including film and other special processed records but specific requirement for temperature /
humidity control have not been provided.
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-5-o GPUSC QC prccedures which are applicable during this period have not been identified, althoegh certain procedures are referm ' i.
o
'Jocumentatt i and docun.9nt distribution requirements have not Deen fully established.
Th'
cem is unresoived pending review by an NRC inspector a couplete long ters storage and maintenance program.
(363/79-07-02)
5.
Reinforcing Steel Removed from Construction Area During inspection of the laydown area for reinforcing steel, the inspector ob erved a small number of bars which appeared to have been 'nstalled and later removed.
These L'rs had not been tagged.
The inspector was informed that a decision hud not been made con-cerning scrapping or storage of these bars for future use.
This item is unresolved.
(363/79-07-03)
6.
Waterstop in Auxilia y suilding During a walkthrough inspection of the Auxiliary Building substruc-ture, the inspector observed that the waterstop in certain areas of the south and west walls was in contact with the rabar. This item is unresolved pending a determination as to whether it had been previously identified during post placement inspection.
(363/79-07-04)
7.
Storage and Preventive Service The inspector observed storage and conformance to preventive service requirements for a random selection of equipment, material, and structures as shown below:
a.
Storage and tagging of rebar in the laydown area.
b.
Building No. 14, Storage of Letdown Heat Exchanger No. CH-C-1 and reactor cooling pipe spools No. 503-01, 503-03, 503-06-1, 2, 3, and 4, 503-09-1, 514-01 and 514-02.
c.
Building No. 13, Boron Concentrator No. CH-2-1.
d.
Building No. 15 (Air Building No. 2), Boiic Acid Filters No.
CH-F-1, 2, 3, 4 and 5.
e.
Steam Generatore :nd Reactor Pressure vessel stored in laydown area.
Inert gas pressure was approaching the lower limit of i244 038
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-6-1.0 psi.
The inspector was informed that a torquing proce-dure had been requested from the vendor (CE) so that hatch covers could be tightened to reduce loss of inert gas.
f.
Building No. 11, Anchor bolts and miscellaneous hardware was being moved into this building.
Extensive rusting was ob-served on some of the anchor bolts No. A-214, Type 7, T-301, T-303, and T-305.
The inspector was informed that the anchor bolts would be examined and, if necessary, protected against rusting.
g.
Substructure of the Containment and Auxiliary Buildings.
The inspector observed work in progress on coating of rebar.
Loose scaffolding and rebar had been removed; conduit was protected by plastic caps; openings to lower levels of the Auxiliary Building and the reactor pit have been enclosed; the structural shapes embedded in the Containment mat have been painted; and the exposed water stops have been painted to prevent deterioration.
The VSL trumpet openings are being protected with plastic caps although this work and coating of rebar is incomplete.
No items of noncompliance were identified.
8.
Curing Records - Placement LSK 406 The licensee identified lack of documentation for curing of this placement during August 13-18, 1978.
This nonconformance has been accumented on NCR No. 0856 and has been dispositioned to require Windsor Probe tests at the time of start of construction.
The inspector had no further questions c,oncerning this matter.
9.
Licensee Action on IE Bulletins and Circulars The inspector examined records and interviewed licensee representa-tives to verify that corrective action had been taken with respect to IE Bulletins shown below:
Bulletin 77-01 (closed):
Pneumatic Time Delay Relay Set Point Drift, Letter FR-1/6090, GPU to B &.R. directs E'& R to assure required repeat accuracy.
Bulletin 77-02 (closed):
Potential Failure Mechanism in Certain Westinghouse AR Relays with Latch Attachments.. Letter FR-1/6419,
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GPU to B & R, directs B & R to obtain necessary documentation if this relay is specified for use.
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-7-Bulletin 78-01 (closed):
Flammable Contact-Arm Retainers in GE CR 120A Relays.
Letter FR-1/E165, GPU to CE and B & R,. directs verification that manufacturers code later than 1973 is provided if this relay is used.
10.
Licensee Action on Previous Inspection Findings (Closed) Noncompliance (78-07-01):
Soil Erosion and Sedimenta-tion Control.
The inspector toured the site and examined onsite soil conditions and measures taken to control erosion; particularly along southern and eastern perimeter of site and the south access road.
A s.edimentation basin with an overflow drain and riprap overflow spillway is uncer construction in the southwest corner of the site.
The entire southern perimeter has been graded to form a berm sloping inward to the basin or to a drai.lage ditch inside the fence line.
Additional hay bales have been intalled along the toe of slope of the filled area and riprap has been placed in washouts on the hill and slope.
Various areas previously sown in rye have been reseeded recently with a permanent cover.
The south access road has been paved, slopes of the adjacent banks have been riprapped and the ditches lined with asphalt covered stone.
These actions also close item of noncompliance 77-02-01.
(Closed) Unresolved Item (78-07-02):
Minor Oil Spill.
The inspector e,amined areas adjacent to equipment storage and maintenance areas and observed no evidence of oil spills.
GPU report E & L-1723, dated June 21, 1979 states that, as part of the construction environmental control program, a complete onsite inspection is conducted at least once a week.
A minor oil spill had been iden-tified in May and had been cleaned up.
(Closed) Noncompliance (78-10-01):
Training of M-K QC Personnel.
- Training had been conducted to correct identified deficiencies and the M-K QC program had been revised.
The revised training program was in progress until termination of the M-K contract.
(Closed) Noncompliance (78-13-01):
Inadequate Preparation of Constructicn Joints.
M-K procedures had been revised to incorporate detailed attributes into the QC checklists.
Use of the checklists had been monitored by GPU QC until termination of the M-K contract.
(Closed) Unresolved Item (78-13-02):
Rock Pockets and Honeycomb in Engineering Safety Compartment Concrete Wall.
The defective areas have been cut out and repaired in accordance with Standard Repair Procedure CP-03-FR and Special Repair Procedure CP-15-FR, Rev. 1.
Repairs have been inspected by QC and the NCR has been closed.
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-8-(Closed) Unresolved Item (78-13-03):
Inadequate Concrete Place-ment Records.
The inspector examined Concrete Placement Records for Placements No. LSK-108, LSK-109-A, B, F and G, and LSK-115 Pour XII.
Records were complete and NCR's written for corrective action.
(Closed) Unresolved Item (78-15-01):
Lack of Follow-up on Defi-ciencies, fdentified dbring surveillance inspection.
GPU QA Procedure FR-10-04, had been revised to require follow-up and reinspection of identified deficiencies.
Review of Surveillance Report Log for the period since December, 1978 shows all unsatis-factory reports closed within a reasonable time.
(Closed) Noncompliance (78-15-02):
Control of Measuring and Test Equipment (M&TE).
T'1e inspector reviewed records showing that the tachometers had.been sent offsite for ? calibration and calibr.stic, i
All M&TE excelt as required for main-records of thermocouples.
tenance has been removed from the site.
(Closed) Unresolved Item (78-15-04):
Cadwelding Reference Marks.
Procedure CP-12-FR is no longer used; M-K Contract cancelled.
(Closed) Unresolved Item (78-16-01):
Concrete Placement No.
LSK-508-2A.
The inspector examined NCR No. 0443 which provided disposition and corrective action as well; result of concrete test program, records of training session and M-K memorandum dated November 29, 1978 which provided instructions for resolution of disagreement between QC and construction.
(Closed) Unresolved Item (78-16-02):
M-K QC Program.
This program had been previously reviewed (Inspection Report 78-01) and is no longer applicable since cancellation of M-K coitract.
(Closed) Unresolved Item (78-16-03):
Reactor Pit Liner Welding.
NCR No. 0027 documents actions to remedy problem due to water trapped below liner plates and PDM letter to S&W dated December 22, 1978 provides procedure for performance of the work.
(Closed) Unresolved Item (79-02-01):
Preventive Service Charging Pumps and Shutdown Heat Exchanger.
Charging Pt,s No. CH-P-1A and CH-P-18 l'ad been transferred offsite on April 5 1979.
No response had been received to S&W letter requesting permt. s.an to add oil.
Equipment Storage History Cards (ESCH's) No. 119, 120, 121 and 122 showed oil changed February 16, 1979.
NCR No. 0228 had been resolved and closed and ESHC's No. 129 and 130 showed inert gas pressure to be within the required limits.
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(Closed) Unresolved Item (79-02-02):
Storage Requirements for Shutdown Heat Exchangers.
The inspector examined storage condi-tions for this equipment.
Area has been cleaned up, access hatch enclosed and the equipment covered and enclosed within a wooden container.
This is considered under present conditions to be equivalent to a closed warehouse.
(Closed) Noncompliance (79-02-03):
Monitoring of Inert Gas Pres-sure.
CE letter J-CS-13, February 16, 1979 revised requirements for monitoring inert gas pressure following changes in temperature /
humidity.
The inspector examined ESHC's for the following items of equipment for the period February 15, 1979 to date:
o Steam Generator ESHC No. 114 o
Steam Generator ESHC No. 115 o
Pressurizer ESHC No. 116 o
RPV Head ESHC No. 117 o
Reactor Pressure Vessel ESHC No. 118 o
Shutdown Heat Exchanger ESHC No.129 o
Shutdown Heat Exchanger ESHC No. 130 These cards showed inert gas pressure to have been monitored daily from February 15, 1979 to March 19, 1979 and weekly thereafter.
(Closed) Noncompliance (79-02-04):
New procedures have not been provided and are not required since cancellation of the M-K con-tract.
11.
Unresolved Items Unresolved items are matters about which more information is required in order to ascertain whether they are acceptable items or items of noncompliance.
Unresolved items disclosed during this inspection are discussed in paragraphs 4, 5 and 6.
12.
Exit Interview At the conclusion of the inspection on June 27, 1979, a meeting was held at the Forked Riser site with representatives of the licensee and contractor organization.
The inspector summarized the results of the inspection as described in the report.
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