IR 05000313/1976015
| ML19309D840 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 11/04/1976 |
| From: | Dickerson M, Madsen G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML19309D822 | List: |
| References | |
| 50-313-76-15, NUDOCS 8004110699 | |
| Download: ML19309D840 (12) | |
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U. S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND EhTORCEMENT
REGION IV
IE Inspection Report No. 50-313/76-15 Docket No. 50-313 Licensee: Arkansas Power & Light Company License No. DPR-51 Sixth & Pine Streets Pine Bluff, Arkansas 71601 Category C Facility: Arkansas Nuclear One, Unit 1 Location: Russellville, Arkansas Type of Licensee: B&W, PWR, 2568 Mwt
Type of Inspection: Routine, Unannounced Dates of Inspection: October 26-29, 1976
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Dates of Previous Inspection: September 20-24, 1976 Principal Inspector:
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O M. W. Dickerson, Reactor Inspector Date Accompanying Inspector: None
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Reviewed By:
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G. L. Madsen, Chief, Reactor Operations &
Date Nuclear Support Branch
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SE29'.ARY OF FINDINGS I.
Enforcement Action A.
Violation None identified during this inspection.
B.
Infractions 1.
Contrary to 10 CFR 50, Appendix B, Criterion V and the licensee contractor's procedure WFMC-1, " Welding Filler Material Control Procedure Specification," Rev. O, paragraph 6.5, the welder did not keep the work area clear of discarded welding filler material as required.
(DETAILS, paragraph 3)
2.
Contrary to 10 CFR 50, Appendix B, Criterion V, drawings were not being controlled by a procedure appropriate to the circumstances. Several drawings were found which did not reflect that modification had been made to the subject system nor did they note that a design change had been approved N
which had modified the system.
(DETAILS, paragraph 4)
C.
Deficiencies None identified during this inspection.
II.
Licensee's Action on Previously Identified Enforcement Matters 75-07 IB/1 Fire Stops Design Control
Several fire stop areas remain incomplete pending receipt of materials.
This matter will remain open pending completion of the work.
75-09 A.1(c) Receiving Inspection. Records The inspector reviewed the licensee's response related to lack of records identifying the details of inspection of a received item
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contained in their letter to the NRC dated September 15, 1975. As
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a result of this review, this matter is considered resolved.
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-3-76-05 IB/l Failure to Follow Procedure
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The inspector reviewed the licensee's response to the NRC dated May 11, 1976, relative to failure to follow procedure 1004.19,
" Hold, Caution and QC Tagging Procedure." As a result of this review, this matter is considered resolved.
76-05 IB/2 Temporarv Changes - Improper Approval The inspector reviewed the licensee's corrective action discussed in their letter to the NRC dated May 11, 1976 regarding the approval of temporary changes. This matter is considered resolved.
(DETAILS, paragraph 2)
76-05 IB/4 Detailed Procedures - Drop Group Rods The corrective action discussed by AP&L in their letter to the NRC dated May 11, 1976, relative to this matter, has been reviewed by the inspector. Additionally, the inspector reviewed procedure 1203.03 "CRD Malfunction Action," Rev. 3, dated August 18, 1975 which includes action to be taken in case of dropped rods. As a result of this review, this matter is considered resolved.
I III.
Design Changes
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Not inspected.
IV.
Unusual Occurrences None identified during this inspection.
V.
Other Significant Findings
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A.
Current Findings 1.
Plant Status During the inspection, the reactor was being operated at 99%
power.
2.
Bearing Failurcs on Westinghouse Vertical Motors used as RHR i
Pump Drivers The licensee indicated that no Westinghouse Vertical Motors are used as RHR pump drivers at ANO-1.
While Westinghouse Motors are used as RER pump drivers, they are horizontal motors and no further action is being taken by the licensee.
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Unresolved Items
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No new unresolved items were noted during this inspectiou.
B.
Status of Previously Reported Unresolved Items
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75-02/2 Control Room Fire System NEL-PIA has replied to AP&L by letter, File No. N-143/N-143, dated August 30, 1976, on the control room halon acceptance test and has stated that the results are acceptable. This matter is considered closed.
76-01 Fire Protection and Prevention The three fire stops in room 105 which were previously sealed wit 1.
" Silicone Rubber," a flammable material, have had the " Silicone Rubber" removed and replaced with a noncombustible sealant. This matter is considered resolved.
76-02/1 CRDM Binding The licensee has determined that the problems encountered with thu CRDM's was due to problems with the latching mechanism and was no:
due to rod binding. This matter is considered closed.
76-02/2 Reporting Personnel Changes The licensee has indicated that the notification to the NRC as noted on figure 6.2-1 of the ANO-1 Technical Specifications relative to personnel changes may be either verbal or written.
This matter is considered closed.
76-05/1 Conflict between QCP 1004.21 and the QA Manual
The conflicts between procedure 1004.21 and the Quality Assurance Manual regarding the approval of temporary changes to procedures has been eliminated. This matter is considered resolved.
(DETAILS, paragraph 2)
VI.
Management Meeting
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A.
Entrance Meeting
A preinspection meeting was held with Messrs. J. W. Anderson and
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L. Alexander on October 26, 1976.
Mr. Anderson was informed that the following items would be reviewed during the inspection:
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1. 'Cleanlinesa 2.
Records 3.
Procurement
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4.
Licensee Event Reports l
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Previous Items of Noncompliance
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Previous Unresolved Items
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B.
Exit Meeting At the conclusion of the inspection on October 29, 1976 an exit meeting was held with representatives of the ANO-1 plant staff.
i The following individuals were present:
J. W. Anderson, Jr., Plant Superintendent M. Bishop, Records Supervisor T. M. Martin, Supervisor Plant Maintenance B. A. Terwilliger, Supervisor Plant Operations L. W. Humphrey, Quality Assurance Engineer
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D. O. Smith, Quality Assurance Engineer i
L. Alexander, Quality Control Engineer
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The inspector discussed the following items:
1.
The noncompliance as a result of failure to follow the procedure regarding weld rod control.
(DETAILS, paragraph 3)
2.
The noncompliance as a result of failure to control drawings which had been modified.
(DETAILS, paragraph 4)
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3.
The resolution of previous items of noncompliance.
(Section II of the Summary of Findings)
4.
The status of previously identified unresolved items.
(Section V.B of the Summary of Findings)
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DETAILS 1.
Persons Contacted l
The followit.g individuals, in addition to those listed under the
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Exit Meeting section of this report, were contacted during this inspection.
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i Arkansas Power and Light Company (AP&L)
G. H. Miller, Assistant Plant Supervisor W. L. McDaniel, Plant Services Supervisor G. M. DuPriest, Shift Supervisor P. W. Jacob, Production Engineer S. S. Strausner, Quality Control Inspector B. C. Austin, Clerk R. L. Hooper, Storekeeper M. J. Jennette, Clerk 2.
Temporary Changes - Improper Approval The inspector reviewed the licensee's corrective action as discussed in the AP&L letter to the NRC dated May 11, 1976. The corrective action included review and approval of temporary change 1 to procedure 1104.03, Revision 4, " Chemical Addition," and approval of Revision 2 to procedure 1103.06, " Reactor Coolant Pump Operation."
The corrective action alac included changes to procedure 1004.21 and the Quality Assurance Manual to remove conflicting requirements.
These changes now allow temporary deviations from established instructions, procedures, or drawings to be made in case of emergency, provided they are approved by two members of the plant staff at least
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one of whom shall be a Shift Supervisor.
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These changes also bring procedure 1004.21, Revision 1, temporary change 1, " Handling of Procedures," and the Quality Assurance Manual into conformance with the Technical Specifications.
3.
Cleanliness The inspector toured selected areas, reviewed procedures and conducted
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discussions with representatives of the licensee's organization to verify that:
a.
Written administrative controls have been established to assure adequate housekeeping and cleanliness.
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Procedures include requirements for material accountability in critical clean areas such as openings in the primary system, work on primary system components, and the refueling area.
c.
Requirements for cleaning primary system compcnents have been established.
d.
Requirements that excessive equipment or material is returned to storage.
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e.
A requirement for prompt removal from the facility of combustible material and debris.
f.
Maintenance personnel are cognizant of and do use the procedures discussed in 'a' through 'e' above.
Review of the procedures indicated that no specific requirements have been established relative to items
'b' and 'e' above. However, procedure 1502.03, " Preparation for Refueling," does contain a j
requirement that all tools and other items over the reactor canal, or pool, must be securely fastened by a safety line, tape, etc.
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The tour established that housekeeping was generally acceptable but
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that some areas such as the waste compactor area and the boric acid tank area needs additional cleaning.
During the tour it was also noted that, while no one was presently at work on the system, work had been in progress on the installation of the unit 2 regenerative vaste system. This system is to be tied into the unit 1 system in accordance with DCR 431 and 431A. On the floor in this area were several stubs of E-7018 weld rod. The inspector noted that this was not in conformance with the contractor's (Bechtel)
pror 'ure WFMC-1, Rev. O, " Welding Filler Material Control," paragraph
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6.5, dated May 1973. This paragraph states that " Individual welders shall keep their work areas clean of unauthorized and discarded weld-ing filler material. Damaged electrodes shall be placed in waste bins and removed from the work area." The inspector informed a represen-tative of the licensee that failure to properly control the weld material was considered an infraction.
4.
Records The inspector reviewed procedures, reviewed records, and conducted discussions with representatives of the licensee's organization to verify that:
a.
The program for the control, storage, retention and retrieval of
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I records and documents conform with Technical Specifications for the following systems:
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(1) Reactor Coolant System (2) Reactivity and Power Control (3) Power Conversion and Auxiliary Systems
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(4) Containment Systems (5) Emergency Core Cooling Systems (6) Other Engineered Safety Features (7) Electrical Systems b.
As-built drawings are being maintained per established procedures.
Record keeping of reactor operations and equipment performance c.
are sufficient to permit review by the licensee personnel to detect long-term equipment degredation or adverse trends that could result in potential safety hazards, as required by Technical Specifications.
d.
Records of changes in the facility, changes in procedures, and
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records of tests and experiments are maintained.
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A sampling of the following selected records met the requirements outlined above, except for item
'b' as discussed below.
(1) Station Log 7/20/76 to 9/7/76 (2) Power Range Recorder 7/14/76 to 9/13/76 (3) "B" Steam Generator Level Recorder 8/9/76 to 9/11/76
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(4) Reactor Building Spray Pump P35B Surveillance Test 8/1/76 (5) High Pressure Injection Pump P36B Rotation and Test 6/16/76 i
(6) NSS and Safeguard Log 7/31/76 to 9/1/76 (7) Diesel Generator #2 Surveillance Test 9/23/76
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-9 The inspector selected those drawings associated with DCR #436,
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Modifications to the Control Room Ventil&tica System, to determine if drawings and modifications to drawings were being adequately controlled. A drawing change request to update the drawings to the as-built condition was submitted on June 11, 1976. The drawings associated with the DCR are as follows:
E-359, Sheet 1, Revision 9, Control Room Ventilation System
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E-359, Sheet 2, Revision 2, Control Room Ventilation System M-185, Revision 5, Ventilation Controls Diagram Control Room, Computer Room and Electrical Equipment Rooms M-263, Revision 5, Ventilation Air Flow Diagram Auxiliary Building, Control Room, Electrical Equipment Rooms, Clean Lab Area E-512, Sheet 8, Revision 14, Connection Diagram 480V Motor Control Center B-56 E-568, Sheet 4, Revision 13, Connection Diagram Main Control Panel C-19
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E-581, Sheet 2, Revision 2, Connection Diagram Heating and Ventilation Panels C-141 and C-204.
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The inspecter determined that for the above listed drawings that there were no indications in the files that a change had been made to the drawings, i.e., the sepias were not stamped or otherwise noted as being obsolete, the drawing card file did not have a card for these drawings indicating a change had been made to the system. Additionally, a check of the latest Drawing Control Register and records of drawing distribution indicated the latest revision to be those enumerated above with no
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j noted changes pending. A check in the shop of two drawings issued to
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the mechanical department showed them to be the revisions shown above but without indication that the system had been modified.
A review of procedure 1004.23, Revision 2, " Drawing Control," dated August 3, 1976, indicated that it is lacking in detail relative to the specific controls necessary to preclude the loss of control of drawings such as that discussed previously. Moreover, the procedure does not describe the actual control mechanisms that are utilized for drawing control at ANO-1.
i The inspector informed the licensee that failure to adequately control the drawings and provide a procedure appropriate to the circumstances
i as required by 10 CFR 50, Appendix B, Criterien V, was considered an infraction. -
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5.
Procurement The inspector reviewed procedures, reviewed records, and conducted discussions with representatives of the licensee's organization and verified that:
a.
Procurement specifications used in the pruchase of components or materials related to the containment system, electrical systems, and other engineered safety features included:
(1) Proper approval (2) Quality control inspection requirements (3) Quality record requirements b.
That documentary evidence is available on-site to support equipment and material conformance to procurement requirements Spare part components or material used in safety related c.
functions:
i (1) Have been inspected upon delivery j
(2) Are being properly handled in accordance with measures
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established for controlling separation of conforming and nonconforming materials, parts and components d.
That the spare part components were supplied by an approved vendor The following pruchase requisitions were selected for review relative to the foregoing requirements:
l fl Requisition No.
Date
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91319 8/3/76 Transformer for 125V DC Battery Charger -
Power Conversion Products, Inc.
I 87456 9/20/76
"0" Rings for Equipment Hatch -
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W. J. Wooley Co.
68424 2/2/76 Spare Parts for RPS and ESAS -
I Bailey Meter Co.
9265 9/9/75 Spaces for P36A, B and C Make up Pumps -
Byron Jackson Co.
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N-11-Requisition No.
Date
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9258 9/15/75 Spare Parts for Primary Temperature Elements -
Balcon & Wilcox 9489 10/15/75 Spara Parts for Decay Heat Removal Pump Room Unit Coolers VUC 1A, 13, 1C & 1D -
H. K. Porter Co., Inc.
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86050 2/5/76 Spares for P36A, B & C Make up Pumps -
Borg Warner Only two of the pruchases had been received (Req. #87456 and 91319).
Certifications were contained in the record files and the components
material were observed to be stored as required.
No discrepancies were noted.
6.
Review of Licensee Event Reports l
The inspector reviewed plant records related to the following licensee
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event reports and verified that the details were clearly reported to
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NRC and facility management; the corrective action described had been initiated to prevent tecurrence; that they had been evaluated as
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required by the Technical Specifications; and that safety limits, limiting safety system settings and limiting conditions for operaticus not exceeded.
^UE 76-1 Alarm for a 0.lg seismic event for Strong Motion Accelerograph Inoperable UE 76-14 Reactor Building cooler unit service water valve CV-3812 failed to open on command
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UE 76-15 A cracked weld in the Resin Sluice Line i
UE 76-16-T-9 was below the 37,500 lb Na2 2 3 Limit per TS 3.3.4.B S0 UE 76-18 Breaker trip on H2 purge and penetration room H&V system
UE 76-19 Failure to perform surveillance test on control roca emergency ventilation system at required frequency UE 76-20 Hydraulic Shock Suppressors empty fluid reservoirs UE 76-21 Pinhole leak on outlet of B radwaste demineralizer
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UE 76-22 Reactor Coolant System leakage in excess of 10 gpm UE 76-23 Failure to comply with surveillance test schedule
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With respect to 76-19 and 76-23 it is noted that these are violations of the Technical Specifications for which corrective
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j action has been accomplishec.
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