IR 05000313/1977013
| ML19320A021 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 09/09/1977 |
| From: | Dickerson M, Madsen G, Westerman T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML19320A007 | List: |
| References | |
| 50-313-77-13, NUDOCS 8004140643 | |
| Download: ML19320A021 (9) | |
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U. S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
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REGION IV
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Report No. 50-313/77-13 Docket No. 50-313 License No. OPR-51 Licensee:
Arkansas Power & Light Company P. O. Box 551 Little Rock, Arkansas 72203 Facility Name: Arkansas Nuclear One, Unit 1 Inspection At: Arkansas Nuclear One Site, Russellville, Arkansas Inspection Conducted: August 30 - September 2, 1977 Inspectors:
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M8/77 M. W. Dickerson, Reactor Inspector Date O
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Y/9f77 9. F. Westerman, Reactor Inspector Date Approved By:
had-9/#77 G. L. Madsen, Chief, Reactor Operations and Date
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Nuclear Support Branch Inspection Sumary Inspection on August 30 - September 2, 1977 (Report No. 50-313/77-13)
Areas Inspected: Routine, unannounced inspection of design, design changes and mcdifications; maintenance; plant operations; safety limits, limiting safety settings and limiting conditions for operations; follow up on inspector identified and unresolved problems; and tour of plant areas.
The inspection involved 63 inspector-hours on-site by two NRC inspectors.
Results: Of the six areas inspected, no items of noncompliance or deviations were found in four areas; two apparent items of noncompliance were found, each in different areas of the inspection (infraction 1 - failure to follow a procedure for the control of drawings, paragraph 3; infraction 2 - failure
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to follow a procedure for the control of jumpers, paragraph 5).
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-2-DETAILS
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1.
Persons Contacted
- J. W. Anderson, Jr., Plant Superintendent
- G. H. Miller, Assistant Plant Superintendent
- B. A. Terwilliger, Supervisor Plant Operations P. Jones, Instrumentation & Controls Supervisor I. J. Butler, Assistant Plant Supervisor Maintenance
- C. A. Halbert, Technical Support Engineer
- T. H. Cogburn, Nuclear Engineer J. Maxwell, Shift Supervisor
- M. Bishop, Records Supervisor
- L. W. Humphrey, Quality Assurance Engineer L. Alexander, Quality control Engineer
- 0. R. Hamblen, Quality Control Inspector
- S. S. Strasner, Quality Control Inspector D. Trimble, Training Coordinator F. B. Foster, Production Engineer M. J. Jennette, Clerk
- Attended exit interview.
2.
Licensee Action on Previous Inspection Findings
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(0 pen) Noncompliance (7710-1): Failure of SRC to conduct audit of the operator requalification program. Additional response to the Notice
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of Violation is being submitted by the licensee.
(0 pen) Noncompliance (7710-2):
Purchase orders issued to Vendors not on the approved list and storage of equipment not in accordance with manufacturers instructions. Additional response to the Notice of Violation is being submitted by the licensee.
(0 pen) Deviation (7710-A): Preventive Maintenance activities not being completed as scheduled. Additional response to the Notice of Deviation is being submitted by the licensee.
(0 pen) Unresolved Item (7617): Procedural conflict between Quality
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Assurance Procedure 1004.01 and Nuclear Services Frocedure NSP-5.
The licensee now indicates that a complete revision of the procedure is necessary. Completion of the procedure for review is now expected October 31,1977.
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s-3-(0 pen) Unresolved Item (7709-3): Formal changes in plant computer hardware, software, review and approval.
The licensee presently has no program for controlling changes to the computer. The licensee indicated that a procedure will be prepared and approved for use by January 1,1978.
(0 pen) Unresolved Item (7711-1): Procedure No. 1304.90 does not require information on the "as-found" as well as the "as-left" condition be recorded. The licensee has indicated that the procedure would be revised by October 1,1977 to provide this information.
(0 pen) Unresolved Item (7711-2): Procedure No. 1302.01 does not require that manufacturers instructions be utilized, nor does it specify that data sheets may be used for simple calibrations.
Moreover, it does not require that acceptance criteria be specified.
The licensee has indicated that a revised procedure to include the foregoing information will be approved for use by January 1, 1978.
3.
Design, Design Change and Modifications The inspector reviewed the licensee's procedures for control of design changes and modifications and their implementation. The following design changes were selected for review:
432 Removal of Reactor Surveillance Completed 6/25/76 Specimen Holder Tubes 436 Modification to Control Circuits Completed 6/25/76 461 Add Alann Acknowledge Button on Completed 3/77 Control Rod Drive System Panel 478 Spent Fuel Storage Racks Completed 5/14/77 480 Modification to Control Circuit of Completed 3/10/77 Pressurizer Relief Valve 483 Replacement of Diesel Generator Completed 3/77 011 Coolers
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-4-During a review of DC 480,. it was found that the specified drawings had not been marked referencing that the DCR was in progress and issued per the Master Drawing Distributicn List (MDDL). This is contrary to the requirement specified in procedure 1004.23, " Drawing Control," Rev. 3, dated June 20, i
1977, which states in part in Section 7.3 that "When work beings on the OCR, the current revision of the drawing is marked
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referencing the DCR in progress and issued per the MDDL...."-
Section 8.2 of the procedure also states that, "When revised drawings are distributed per MDDL, the responsible shop or individual returns the signed Transmittal Sheet to ANO drawing control indicating their receipt, their files are updated and old revisions are destroyed." Contrary to this requirement, a check of the drawings specified in the design cheqe showed that the Technical Support Group had Rev. 6 of M-416 sheet 2 instead of Rev. 7.
The Electric Shop had Rev.14 of E-546,
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sheet 3 instead of Rev. 15 and the Instrument Shop had both Rev.10 and Rev.11 of M-586 in their files. A check of the
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Transmittal Sheets for each of these showed them to be signed indicating the latest revision had been received and that outdated revisions had been destroyed. Rev. 10 of M-586 was destroyed by the licensee prior to completion of the inspection.
O The inspector informed the licensee that the failure to mark
and issue drawings. indicating a design change in progress and the failure to properly control the drawing distribution was in nonconformance with procedure 1004.23 and is an infraction.
Drawings specified by design change 480 were:
08034778E #5 Rev. 3 Schematic
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M-416 Sheet 2 Rev. 7 Logic Reactor Coolant System E-262 Sheet 2'
Rev. 7 Wiring Diagram Plant Auxiliary CC E-204 Rey 13 Schematic Diagram PRV E-558 Sheet 1 Rev. 14 Connection Diagram C04 E-546 Sheet 3 Rev. 15 Connection Diagram C47 M-586 Sheet 1 Rev. 11 CD4 Arrangement E-69 Rev. 32 Circuit & Raceway Schedule 08034778F #4 Rev. 4 RCC Schematic DCN #7 to M230 Rev. 13 RCS P&ID l
l The inspector had no further questions in this area.
4.
Maintenance The inspector completed a review of the licensee's program for the maintenance activities for safety related systems and components.
The following Job Orders were reviewed:
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-5-1639A Overhaul PSV-1000, Pressurizer Electromatic Relief Valve 1885 Trouble Shoot & Repair - P35A 1887 RB Spray Valve CV 1052
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1905 CRD Stator Replacement, Rod 8 Gr. 4 1908 CV-2670 Emergency Feed Block "A" OTSG 2012 Station Battery, Quarterly Test 2016 DG Monthly Test 2104 Inspect Hydraulic Shock Suppressors -
2106 Change F-2 Seal Injection Filter 2111 Repair 021005 "A" Filtered Waste Pump Discharge Drain Valve
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No items of noncomplaince or deviations were identified.
5.
Plant Operations a.
Inspection Scope J
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The inspector reviewed the following shift logs and operating records:
Station Log (8/10-30/77)
NSS & Safeguard Auxiliary Log (8/8-28/77)
ESAS Shift Check Log (8/8-28/77)
RPS Log (8/8-28/77)
Operations Memorandum Standing Orders Jumper Bypass Log Trouble Reports (0 pen)
The inspector conducted a tour of accessible areas and included observations (as appropriate) of the following:
Monitoring Instrumentation Radiation controls Plant Housekeeping Conditiens Fluid Leaks Piping Vibrations Pipe Hangers / Seismic Restraint Selected Valve Position and Equipment Control Switches Lockout Tags Lighted Annunciators Plant Tours Control Room Manning b.
' Inspection' Findings
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The inspector noted that entries in tha Bypass - Jumper
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Log had not been cleared following completion of the l
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j associated activities. This included tags76-231; 77-13, 77-24; 77-22-2, 77-22-1, 77-21-2, 77-21-1, 77-87 and cther tagged and non-tagged entries.
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Plant Procedure 1005.04, Rev. 3 (7/28/77) " Control and Use of Bypass and'Jumeprs" Section 6.1.6 -+ates in part, "A verification of removal of a jumper or bypass or the reinstatement of a lifted leau is to be carried out and documented in a similar manner as-delineated in section 6.1.4 concerning the installation
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of jumper bypasses and lifted leads." Section 7.1 states in part, "... The Shift Supervisor is responsible for assuring that the log is reviewed on a monthly. basis for completed sheets...." The failure to implement and maintain compliance with a procedure designated in Section A.10 of Regulatory Guide 1.33 is contrary to section 6.8.1 of' the Technical Specifications which states in part,~ " Written procedures shall be established, implemented, and maintained cover-ing the activities referenced below:
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The applicable procedures recommended in Appendix "A" of Regulatory Guide 1.33, November 1972...."
The licensee did, prior to the inspector leaving the i
site, remove all Bypass Jumper Logs entries that l
required documentation of clearance, and verbal instruction was issued to personnel involved, includ-O ing technicians and supervisory personnel to preclude recurrence. The licensee was infomed that this would be an item of noncompliance; however, no reply would be required.
6.
Technical Specifications: Safety Limits, Limiting Safety Systems Setting, an Limiting Conditions for Operations (SL, LSSS, and LCO)
a.
Inspection Scope The inspector's review included:
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Discussions with plant personnel regarding selected portions of Technical Specifications (SL's, LSSS.'s, and LCO's).
Direct observation of process instrumentation.
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Review of Reactor Trips (1976 - 1977)
Review of Master Surveillance Schedules to detemine that schedules are being maintained current.
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Inspection Findings The inspector had only one major finding from this inspection effort. The heatup and cooldown curves in the Technical Specification (TS), Section 3.1.2, will require revision
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by the middle of September 1977. This is based on the present plant projected power levels. Tha present TS's curve is adecuate for up to 1.7 X 106 MWt-days.
The licensee,had by letter dated July 6,1977 to NRR, requested the change by October 1,1977.
The licensee stated, follow-
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ing discussions with the inspector, that NRR would be requested to revise the TS at an early date and prior to September 15, 1977.
This item is considered unresolved and is designated 7713-1.
7.
Annual Operating Report The inspector reviewed the revised Annual Operating Report submitted by the licensee on August 5,1977 as a result of the licensee's review of the report and inaccuracies in the report originally
submitted March 1,1977 (See IE report 77-06).
No items of noncomplaince or deviations were identified.
8.
Review of Licensee Event Reports
The inspector conducted a follow up review of two licensee event
reports which had been previously reviewed during an in-office review.
It was determined from the reviews that:
(1) reporting requirements had been met; (2) proper licensee reviews had been conducted; and (3) proper corrective action had been taken.
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Follow up review of the following LER's was made:
77-9 Valve CV-2123 in t'he Penetration Room Ventilation System Found Inoperative.
77-12 Leak in the Spent Fuel Cooling System LER's which were reviewed in the office prior to the inspection were:
77-10 Failure to Perform Complete Surveillance Test on
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l R.B. Escape Hatch I
77-11 Failure to Perfann Surveillance Test at Required Frecuency on Ci Pu-Be Source 77-13 Failure of R.B. Cooling Fan 77-14 Standby Circuit of Penetration Ventilation System Found Inoperative No items of noncompliance or dev.iation were identified.
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Review of IE Circulars The following IE Circulars sent to the licensee were verified to have been received, reviewed for applicability and that appropriate action was taken or is planned.
77-03 Fire Inside a Motor Control Center 77-04 Inadequate Lock Assemblies 77-05 Liquid Entrapment in Valve Bonnets 77-06.
trfects of Hydraulic Fluid on Electrical Cables.
77-08 Failure of Feedwater Sample Probe 77-10 Vacuum Conditions Resulting in Damage to Liquid Process Tanks No items of noncompliance or deviations were identified.
10. Unresolved Items Unresolved items are matters about which more infonnation is required
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in order to ascertain whether they are acceptable items, items of noncompliance, or deviations. The following unresolved item was identified during the inspection:
7713-1 Required Revision to Heatup and Cooldown Curves, paragraph 6.b.
11. Exit Interview An exit interview was conducted on September 2,1977 following completion of the inspection. At the interview the inspector discussed the findings indicated in the preceding paragraphs.
The licensee acknowledged these findings.
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