IR 05000313/1979006
| ML19289F578 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 04/03/1979 |
| From: | Johnson W, Spangler R, Westerman T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML19289F568 | List: |
| References | |
| 50-313-79-06, 50-313-79-6, 50-368-79-06, 50-368-79-6, NUDOCS 7906150055 | |
| Download: ML19289F578 (18) | |
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEF'_2T
REGION IV
Report Nos. 50-313/79-06
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50-368/79-06 Docket No.
50-313 License No. DPR-51 50-368 NPF-6 Licensee:
Arkansas Power and Light Company P. O. Box 551 Little Rock, Arkansas 72203 Facility Name: Arkansas Nuclear One (ANO), Units 1 and 2 Inspection At: AN0 Site, Russellville, Arkansas Inspection Conducted:
February 12 through March 18, 1979 Inspectors:
2 [. [Alb v/ T/ M T. F. Westerman, Chief, Reactor Projects Section Date'
!//lb 4/3/79 mm V.'D.pnson,ReactorInspector Date 7 $. M k V/rh1 R. G. Spangler, Reactor Inspector Date Approved By:
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V/3/79 G. L. Madsen, Chief, Reactor Operations and Date Nuclear Support Branch Inspection Sunmary 2228 333 Inspection conducted during sriod of February 12 through March 18, 1979 Report No. 50-313/79-06)
Areas Inspected: Routine, announced inspection of previously identified inspection followup items, previous items of noncompliance, surveillance, drawing control, and IE Bulletins and Circulars. The inspection involved 39 inspector-hours on-site by one (1) NRC inspector.
Results: Within the four areas inspected, no items of noncompliance or deviations were identified.
7006150CS6
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-2-Inspection conducted during period of February 12 through March 18., 1979 Report No. 50-368/79-06)
Areas Inspected: Routine, announced inspection of previously identified inspection followup items, previous items of noncompliance, design change and modification, drawing control, review of 20% power level plateau data, IE Bulletins and Circulars, witness of licensee QA audit, licensee event reports, and independent inspection effort.
The inspection involved 143 inspector-hours on-site by three (3) NRC inspectors.
Resul ts : Within the nine areas inspected, one item of noncompliance was identified relating to control of non-Class 1E test equipment (Details, paragraph 7.a).
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-3-DETAILS 1.
Persons Contacted Arkansas Power & Light Company Employees J. P. O'Hanlon, AN0 Plant Manager G. H. Miller, Engineering & Technical Support Manager L. Alexander, QC Engineer B. A. Baker, ANO-2 Operations Supervisor T. N. Cogburn, Nuclear Engineer E. C. Ewing, Production Ste* tup Supervisor D. R. Hamblin, QC Engineer T. Holcomb, Scheduler P. Jones, Maintenance Supervisor S. M. Strasner, QC Technician B. A. Terwilliger, Operations & Maintenance Manager J. Robertson, ANO-1 Operations Supervisor S. Petzel, Licensing Engineer F. Foster, Plant Administrative Manager M. Stroud, Electrical Maintenance Supervisor J. Lowman, Assistant I&C Supervisor R. Elder, I&C Supervisor R. Tucker, Assistant I&C Supervisor J. McWilliams, Planning & Scheduling Supervisor R. Beta, QA Engineer J. Brown, QA Engineer Combustion Engineering
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S. McGregor, Chief Startup Engineer 2.
Plant Status Unit 1 Plant has returned to 100% power. The plant is to be shutdown March 30, 1979 for a planned refueling outage.
Unit 2 The plant was shutdown following testing at the 20% power plateau.
Preparations are being made to resume testing at the 50% power plateau following repairs and modifications to all four reactor coolant pumps.
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-4-3.
Inspector Followup on Previously Identified Items a.
Unit 1 (Closed) Item of Noncompliance (Inspection Repori. 78-12, para-graph 14):
Failure to perform a monthly surveillance test of Unit 1 nonsupervisory fire protection circuits.
Procedure 1004.12A, Master Surveillance Test Schedule, has been amended to include an entry for this surveillance test.
Furthermore, the Electrical Maintenance Supervisor has added Surveillance Procedure 1405.14, " Monthly Surveillance of Non-supervisory Fire Protection Circuits," to his Unit 1 surveillance schedule.
(Closed) Item of Noncompliance (Inspection Report 78-12, para-graph 11):
Control of Weld Rod.
The ANO staff has implemented administrative controls to provide for the control of weld processes and materials, Procedure 1004.09,
" Control of Welding," has been approved and issued.
Furthermore, Permanent Change i to Proceduie 1004.15, " Control of Weld Rod,"
now requires daily return of portable weld warmers to the store-room.
(Closed) Item of Noncompliance (Inspection Report 78-16, para-graph 3):
Failure to verify the removal of bypass tag numbers 77-121-1 and 77-121-2.
The inspector verified that the log entries for the above bypass tags were completed and that appropriate instructions had been issued to remind personnel of the requirements of Procedure 1005.04,
" Control and Use of Bypasses and Jumpers."
In addition, the Quality Control Group performed inspection number P-16-78 on November 28, 1978 of the Jumper and Bypass Log as a followup to this item of noncompliance.
(Closed) Item of Noncompliance (Inspection Report 78-21, paragraph 9):
Changes to Procedure 1304.30 were not made in accordance with the requirements of Technical Specificatioc 6.8.3.b.
Permanent Change 1 to revision 4 of 1304.30, " Hydrogen Pc le Analyzer and Flow Indication Instrument Surveillance,"' was issued to incorporate the changes to data sheets noted in paragraph 9 of Report 78-21.
The inspector also verified that personnel have since been instructed in the requirements of the Technical Specifications with regard to changes to procedures.
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-5-(Closed) Item of Noncompliance (Inspection Report 78-10, paragraph 16):
Failure of operators to receive e.n annual evaluation of actions taken in regard to abnormal or emergency conditions.
The inspector noted that the AND Training Pl<a had been amended on February 23, 1979.
Training Division personnel are now required to review and certify their training summary sheets prior to transferring training records to the vault.
This completes the inspector's review of closcout action in regard to this item of noncompliance.
(Closed) Unresolved Item (Inspection Report 78-12, paragraph 13):
Polling of the Unit 1 Plant Safety Comittee.
The Chairman of tha Plant Safety Comittee (PSC) has stated that the PSC will not use individual ballot or polling techniques in the course of its business.
The inspector now considers this matter resolved.
(Closed) Unresolved Item 78-22-04 (Inspection Report 78-22, paragraph 4.b):
Drawing M-236 for the Sodium Tiosulfate System does not agree with the as-built system.
NCR number 79 has been issued to correct the nonconforming drawing M-236.
The generic aspect of drawings accurately reflecting the Unit 1 "as-built" systems will be addressed by NCR number 75.
This item is considered closed.
Further inspection activity in this area will be tracked by the inspector against open item 79-02-08.
See paragraph 11 of this report for additional details.
(Closed) Unresolved Item (Inspection Report 77-25, paragraph 2.b):
Inspector qualifications for new fuel receipt.
Permanent Change 1 to Procedure 1503.02, " Fresh Fuel Inspection and Storage," requires that an individual shown on the Quality Control Engineer's list of Qualified Inspectors perform the new fuel receipt inspection.
Several of the Nuclear Engineers have been certified as qualified inspectors by participation in vendor
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training (for B&W fuel, CE training is being scheduled), previous fuel receipt inspections, and a review of the pertinent plant procedures.
This item is considered satisfactorily resolved.
(Closed) Open Item (Inspection Report 78-21, paragraph 4):
Control of combustibles in safety-related areas.
Procedure 1005.17, " Control of Combustibles," has been approved and issued as part of the ANO fire protection plan to establish controls and limits on the amounts of allowed combustibles in safety-related areas.
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-6-(Closed) Open Item (Inspection Report 77-25, paragraph 2.b):
Use of a CEA to verify fit on nc'w fuel assemblies.
Appendix B and Form NFil-2 to Procedure 1503.02, " Fresh Fuel Receipt," now requires that a CEA be used to verify proper fit during the new fuel receipt irspection.
b.
Unit 2 (Closed) Unresolved Item 7815-1 (Inspection Report 78-15):
Formal procurement instruction 5 regarding 10 CFR 21.
The preprinted procurement requisition forms now impose Part 21 requirements on all Quality Assured Material.
(0 pen) Open Item (Inspection Report 78-01, paragraph 3):
Vendor reappraisal as it relates to equipment history.
Exhibit V to 1004.06, Rev. 4, now provides for the site Quality Control organization to initiate feedback on vendor performance.
The licensee's QA organization has indicated that an interface with the newly established Nuclear Powerplant Reliability Data System as a feedback mechanism for vendor performance would be evaluated.
(Closed) Open Item (Inspection Report 78-12, paragraph ll.a):
CPC response time testing.
Response time testing of the RTD's associated with the CPC was completed prior to entry into Mode 2 startup testing. This was accomplished by dunking the RTD's which were incased in a typical well into a moli.en metal bath.
The original data for the RTD's was without a well.
(Closed) Open Item (Inspection Report 78-25, paragraph 2):
Computer alarm and sequence of events printouts.
Review and modification of computer alarm and sequence of events computer printouts have been completed.
(Closed) Open Item (Inspection Report 78-25, paragraph 6.e): Training for maintenance personnel on instrument inverters.
Training for maintenance personnel on new Procedure 2304.88,
" Vital AC Inverter Test and Inspection," (1/9/79, Rev. 0) was verified by the inspector.
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-7-(Closed) Open Item (Inspection Report 78-28, paragraph 9):
Calibration accuracy for 2LI-2801 and 2821 - Emergency Diesel Day Tank Level Indication.
An accuracy of + 2 error has been established and is being entered into the computer PM program.
(Closed) Open Item (Inspection Report 78-28, paragraph 12.b(2)): Licensee Event Report for misaligned or dropped control rods.
LER 50-368/78-23 has been submitted to document all misaligned or dropped control rods that occurred daring Mode 2 startup testing.
(Closed) Unresolved Item 368/79-02-07 (Inspection Report 50-368/79-02):
Design Control / Technical Specification changes as related to LER 50-368/78-14.
As discussed with the licensee, it is apparent that the problem with this design change as reported in LER 50-368/78-14, came about as a result of a disagreement between AP&L and their major contractor on the acceptability of two different test reports.
The end result was that the original Technical Speci-fications were not really affected.
(Closed) Open Item (Inspection Report 78-26, paragraph 17):
Deficiencies in Operations Procedure 1005.25 as ralated to Unit 2 records retention.
OP 1005.25 has been deleted. All records are being entered into a computer retention system.
(Closed) Infraction (Inspection Report 78-29):
Fire doors not properly closed.
Plant operators have been instructed to check the status of fire doors during their tours. The waste control operator log sheet has been revised to require recording a fire door check once per shift.
(Closed) Infraction (Inspection Report 78-29):
Control of combustibles.
The inspector reviewed the licensee's corrective action on this item and had no further questions.
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(Closed) Infraction (Inspection Report 78-29): Jumper Log discrepancies.
The inspector reviewt.d the licensee's corrective action, includ-ing memo AN0-0625, and had no further questions.
(Closed) Infraction (Inspection Report 78-25):
No surveillance test procedures established for 120V AC inverters 2Yll, 2Y13, 2Y22 and 2Y24.
The licensee has established the required procedures and trained the electrical maintenance group in their use.
(Closed) Infraction (Inspection Report 78-23):
Failure to perform monthly surveillance checks on ACS 8001 and ACS 8002.
Surveillance Procedure 1304.68 has been established by the licensee, and it is being performed on a monthly frequency.
(Closed) Infraction (Inspection Report 78-26):
Nonfunctional fire barriers.
No written response to this infraction was required.
The inspector reviewed the licensee's corrective action on this item and had no further questions.
(Closed) Deficiency (Inspection Report 78-28):
Failure to retain records of set point changes.
The inspector reviewed a licensee internal memo, AN0-232, 2-150, addressed to I&C Supervisors and Technicians, which pointed out the requirement for retention of procedural attachments to job orders which change set points.
(Closed) Infraction (Inspection Report 78-28): Test interval exceeded for channel functional test for 2XR-8350.
The inspector reviewed the new I&C surveillance schedule and had no further questions.
(Closed) Infraction (Inspection Report 78-29):
Failure to follow procedure sequence for control rod withdrawal.
The inspector reviewed licensee internal memo, AN0 0468, and the records of licensed operator review of this memo and the associated inspection reports.
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-9-(0 pen) Open Item 368/78-29-01 (Inspection Report 78-29, para-graph 3):
Revision of Procedure 1005.01 to include organization changes.
The necessary revision was in process at the time of this inspection.
(Closed) Open Item 368/79-02-01 (Inspection Report 79-02, para-graph 16.a): Modification of deck grating to remove interference with 2CV-1075 for manual operation.
This item was completed on February 7,1979 under Job Order 2-3531-79-1.
(Closed) Open Item 368/79-02-02 (Inspection Report 79-02, para-graph 16.d): BAM tank level out-of-specification.
LER 79-17 has been submitted by the licensee to close this item.
(Closed) Open Item 368/79-02-03 (Inspection Report 79-02, para-graph 9): Maintaining current operating procedures in test packages.
The Production Startup Supervisor sent a memo to test engineers reminding them of their responsibilities in this area.
(Closed)OpenItem 368/79-02-04 (Inspection Report 79-02, para-graph 12.a):
Resubmittal of LER 78-15 as a 14 day report.
The Plant Safety Committee approved a revision to LER 78-15, changing it to a 14 day report.
(Closed) Open Item 368/79-02-06 (Inspection Report 79-02, para-graph 12.b):
Reportable items.
The licensee is submitting LER's 79-18, 79-19 and 79-20 as required.
(0 pen) Open Item 368/79-02-09 (Inspection Report 79-02, para-graph 4): Revision of QCP 1004.14 to reflect the activities of the Planning and Scheduling group in handling Job Orders.
Licensee action on this item was just beginning at the time of this inspection.
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-10-(0 pen) Open Item 368/79-02-11 (Inspection Report 79-02, para-graph 13.d):
Degraded voltage event.
At the time of this inspection, the licensee was preparing an informational report on this item.
(Closed) Open Item 368/79-G2-12 (Inspection Report 79-02, para-graph 13.d): Plant management review of the Test Chronological Log.
Unit 2 Shift Supervisors have been directed to rcview the Test Chronological Log at the end of each shift.
4.
Safety Review Committee (SRC) (Units 1 & 2)
The inspector reviewed with the licensee the Technical Specification (TS) requirements (Section 6.5.2) for the SRC.
During this review it was pointed out by the inspector that in several areas the charter had not been updated to the requirements of the Unit 2 TS. This included the following Unit 2 TS items:
The fluclear Safety Consultant had not been included.
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- The quorum requirements for Unit 2 is four vice three for Unit 1.
- One additional review item (h) has been included in the Unit 2 TS that does not appear in the Unit 1 TS.
TS 6.5.2.8 One additional audit item (j) has been included in the
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Unit 2 TS that does not appear in the Unit 1 TS.
TS 6.5.2.10 - Minutes of the SRC require 14 day processing for Unit 2 vice 30 day processing for Unit 1.
The inspector was shown, prior to the completion of this inspection, a revised charter which incorported all the above comments.
Approval of the new charter was scheduled for the next SRC meeting in April 1979.
The secretary of the SRC has, following this inspection, established a punch list of committee review items.
Compliance with all the review items of the TS is being evaluated to determine where the review process can be improved.
The inspector pointed out that although the TS requires review only for 14 day reports, some 30 day report items fall under other review requirements of the TS.
Also, some of the QC surveillance findings which are not written up in nonconformance reports may require committee review.
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The inspector has stated that the review performed by the committee will be looked at in detail on a future inspection. This item is considered unresolved.
(50-368/79-06-04)
There were no items of nonccmpliance or deviations identified.
5.
Surveillance (Unit 1)
The inspector reviewed records for selected surveillance tests to determine that the activities were conducted in accordance with adequate and properly approved procedures and in conformance with the requirements of the Technical Specifications.
In addition, the inspector also reviewed the licensee's pump and valve inservice inspection program.
The following procedures were selected for review:
Number / Supplement Title Technicial Specification 1104.33/III Reactor Building Atmosphere 4.5.2.2.2 Control 1107.01/I Electrical System Operations 4.6.2.4 1104.32/III Fire Water System Operations 4.20.1.b 1103.15/ A-2 Reactivity Balance Calculation 4.9 1304.37 Reactor Protection Channel ' A'
4.1 Test 1102.01/3 RCS Leak Test 4.3 1304.92 Measurement of Gap Between the Table 4.1-2.12 bbin FW Lines and the Flow L'imiting Annulus at the RB Penetration 1005.08 ASME Code Section IX Operational 4.2.2 The inspector had no adverse findings as a result of the review of surveillance activities required by Technical Specifications.
In the area of the ASME Code,Section XI testing, it appears that the licensee is accomplishing this testing by incorporating Section XI requirements into the existing surveillance program.
However, the inspector found that the management of this testing program is not being conducted according to the system established by Procedure 1005.08.
For example, Procedure 1005.08 requires that the Operation Supervisor maintain a valve exercise list that, as a minimum, shall contain:
a.
Procedure by which the valve is tested.
b.
Last date the valve was tested.
c.
Next scheduled test date.
This list is not maintained.
1005.08 further states that the Instru-ment and Controls Supervisor shall maintain a valve Leak Test Schedule that shall, as a minimum, contain:
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-12-(1)
Valve number and noun description.
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Procedure number by which it is tested.
(3) Last date tested.
(4) Maximum leak rate.
(5) Last three measured leak rates.
(6) Next schedul'ed test date.
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(7) Valve size.
This list is not maintained.
The licensee is not following an approv-ed procedure; however, the required Section XI testing is being con-ducted.
It is the licensee's intent to change 1005.08 pending the completion of NRR's review of the licensee's submitted ISI program.
In view of this continuing review, this item is considered by the inspector to be an unresolved item (313/79-06-01).
The licensee has been informed that his methodology of conducting Section XI testing and the description of such in Procedure 1005.08 must agree.
No further items were found in the areas.
6.
Closeout Action for Bulletins (Unit 1)
ANO, Unit 1, is not required to respond to IE Bulletins 78-12,78-12A and 78-128 by virtue of having first identified the problem of atypical weld filler material in the reactor vessel as a reportable occurrence.
The licensee's corrective action is being tracked by RIV as followup to LER 78-19.
7.
Licensee Event Followup (Unit 2)
The Licensee's Event Reports (LER) were reviewed by the inspector for:
Corrective Actions
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Operational Safety
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Reporting Requirements
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Administrative Review
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Licensee Event Reports 78-18, 19, 20, 22, 23, 24, 25, 26, 28, 29, 30, 31, 32, 33 and 34; and 79-01, 02, 04, 05, 06, 07, 08, 09,10,11,12, 13,14,15,16,17 and 18 were reviewed by the inspector.
The following items were identified by the inspector as the result of this review.
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-13-a.
Failure to Remove Test Equipment from Channel
"B" CPC (LER 50-368/79-11)
The failure of channel
"B" CPC resulted from the movement of test cables which had been left installed even after the Job Order 5084 which installed them had been closed.
The Job Order was issued on December 11, 1978 to January 15, 1979.
The test cable was still installed when the event occurred on January 25, 19?]. The licensee has been advised by the inspector that the connecting of non-Class 1E test equipment to a IE seismic component vegrades the design intent of that component and the component sNuld be con-sidered inoperable per the Technical Specifications (TS).
It has also been pointed out that normal testing and surveillance can be performed within the constraints of the TS.
It is not apparent that adequate controls have been established over testing of Class 1E components. TS Section 6.8.1 states in part that " Written pro-cedures shall be established, implemented and maintained covering the activities referenced below:... c.
Surveillance and test activities of safety-related equipment." The failure to establish proper controls is considered an item of noncompliance.
TS Table 3.3-1 would allow one channel of CPC to be made inoperable for one hour at which time it has to be tripped or bypassed. After 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> the channel is either made operable or tripped.
During the majority of the time the test cables were installed, Channel
"B" CPC appeared to have been left in operate.
b.
Power Pertubation Channel "B" CPC (LER 50-368/79-06)
Final corrective action to resolve this LER is still under review.
Possible installat' ion of sola transformers is being considered.
The event remains open.
c.
Heat Trace Related Problems (LER's 79-01, 02, 08 and 10)
These four LER's all related to apparent heat trace problems.
These problems include apparent failure to re-energize circuits following maintenance, and in one case failure to close the trans-mitter door on the refueling water storage tank following maintenance activities.
During review of these event reports, the inspector also found that there are apparent design problems with the heat sink effect of pipe supports. The inspector was informed that there are alarm circuits to the control room that have been disconnected.
The inspector was unable to determine if there has been adequate permanent corrective action. This matter has been brought to the licensee's attention and will be followed up on a future inspection.
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-14-d.
Inoperable Emergency Feedwater Pump (LER 78-32)
This LER was not closed during this inspection and will require further followup.
There were no items of noncompliance or deviations identified.
8.
AP&L QA Audit of Startup Test Program (Unit 2)
The' inspector witnessed an AP&L QA audit of the records associated with Test Procedure 2.650.11, " Post Reactor Coolant System Expansion Measurements." The audit was performed in accordance with QA Procedure ANO 17.
There were no items of noncompliance or deviations identified.
9.
NPF-6, Amendment 1, License Condition (Unit 2)
The inspector verified that redundant position indication has been provided for 2-CV-5628-2 as outlined in item M page 12 of amendment 1 to NPF-6.
The Design Change Package (DCP) 448 was dated as complete on May 12,1978.
There were no items of noncompliance or deviations identified.
10.
Design Changes and Modifictions (Unit 2)
'he inspector completed the review of design control for Unit 2 by examining selected design changes to determine that these changes and modifications are in conformance with the requirements of the Technical Specifications and 10 CFR 50.
TM f-liv;s.g design changes for Unit 2 were reviewed.
DC Number Title 79-2002 Removal of the J-26 Connector in 2C-24 2-44 Install Rosemont Pressure Transmitters 2-21 Move Reactor Water Makeup Relief Valve 2PSV-4943 2-15 Replace CPC Optoisolator Boards 2-16 Change to Charging Pump Start Circuitry No items of noncompliance or deviations were identified in this portion of the inspection.
11.
Drawing Control (Units 1 and Unit 2)
The issue of the correctness of Unit 1 drawings and the Unit 2 drawing control problem identified in Inspection Report 79-02 was discussed with the Station Manager during the exit interview and also via a telephone conversation on February 23, 1979. With regard to Unit 1, the 2228 346
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-15-inspector's concern is that the incorrect "as-built" drawing for the Sodium Thiosulfate System (see Inspection Report 50-313/78-22, paragraph 4) may indicate a generic problem with the accuracy of the Unit 1 "as-built" drawings. Also, during the review of Unit 2 design changes detailed above, the inspector noted that none of the drawings involved had been update.1 to show the current "as-built" system.
The AN0 Plant Manager has compiled a listing of the noncurrent Unit 2 drawings and those Unit 1 drawings that are marked "DCR in Progress" but have not been reissued with the completion of the design change.
AN0 management has not yet established a timetable for correction of this problem. The inspectors will continue to monitor this item as followup to open item 79-02-08.
12.
Review of " Millstone Syndrome" Fix - Independent Inspection (Unit 2)
The inspector reviewed several of the design change packages which implemented portions of F design changes for the so called " Millstone Syndrome" electrical proviem. As a result of this review, the inspector had the following findings.
Relays 162/309-1 and 162/409-1 were found to have a time delay setting of three seconds.
Drawing E-2097, Revision 11, shows that these relays should be set at a time delay of two seconds.
The licensee indicated that a Job Order would be issued to reset the above relays.
The recalibration of these relays and the related question regarding the accuracy of other relay settings involved in the design changes will remain as an.open item (368/79-06-01).
Proceduras 1304.90 and 2304.90, "Offsite Undervoltage and Protective Relaying," should be reviewed and updated to include the testing of additional relaying added by the design changes noted above. This item will remain as an open item (313/79-06-02 and 368/79-06-02).
During the review of records associated with the calibration of protective relaying for some of the engineered safeguards equipment electrical breakers, the inspector was not able to identify a com-prehensive program for the scheduling and conduct of relay inspection and test. This item will remain as an unresolved item review by the inspector (313/79-06-03 and 368/79-06-03)pending further
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13.
Review of 20% Power Plateau Data (Unit 2)
The inspector continued the review of the 20% Power Plateau Data and attended the February 13, 1979 Plant Safety Committee (PSC) meeting and the Test Working Group (TWG) meeting during which the 20% power 2228 347
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-16-plateau test data was discussed.
During this review, it was noted that the PSC was required by plant procedures to review only certain power ascension test results.
Specifically, the PSC is only required to review test results having a deficiency against an acceptance criteria that TWG recommends accept as is. The Chairman of the PSC was in general agreement with the various arguments presented by the inspector for PSC cognizance of all test r:sults and deficiencies.
He agreed to have a presentation given to the PSC of all current test results, any deficiencies and their resolution, prior to proceeding to the next power plateau.
During this
.#ection, the inspector also reviewed certain tests performed at the 20% power level plateau.
Items considered in this review included licensca evaluation of test results, acceptability of test data, resolution of deviations, correction of test deficiencies and administrative control of testing.
Tests reviewed during this inspection included the following:
Test Title 2.400.01, Appendix L Process Monitor Intercomparison 2.80v.01, Appendix T CEA Shadowing Factor Verification 2.800.01, Appendix Q CPC/COLSS Verification 2.800.09 Vibration Monitoring At the time of this inspection, the licensee had not yet completed his review and evaluation of test results, and some P_st deficiencies were still outstanding.
This inspection effort will be continued during the next inspection.
No items of noncompliance or deviations were identified.
14.
IE Bulletins and Circulars (Unit 2)
a.
IE Bulletins The inspector verified by record review, observation and discussion the following items with regard to licensee response to IE Bulletins:
Distribution for review
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Records a allable to support reply
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Corrective action completed
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Reply was prompt
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The status of the Bulletins reviewed by the inspector is as follows:
79-01, Environmental Qualification of Class 1E Equipment -
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Licensee's response is still in preparation.
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-17-78-14, Deterioration of Buna-N Components ASCO Solenoid -
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Sent for information only.
No further action by the licensee or RIV is planned with regard to this Bulletin.
78-12 and 12A, Atypical Weld Material in Reactor Pressure
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Vessel - A final reply has not been submitted.
77-05 and 05A, Electrical Connector Assemblies - Licensee's
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final January 30, 1979 response did not include humidity and radiation qualifications for the NSSS supplied connectors.
b.
IE Circulars The inspector verified receipt and review for applicability and corrective acticr for th9 following IE Circulars.
The status of the Circulars reviewed by the inspector is as follows:
79-02, Failure of 120 Volt Vital AC Power Supplies -
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Since this Circular was originated as the.esult of the September 16, 1978 event at ANO and the actions recommended in this Circular have been responded to by AP&L.
This Circular is considered closed.
78-18, Underwriters Laboratory Fire Test -
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Licensee is still in the process of reviewing this item.
78-17, Guard Training -
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Licensee's review of guard training has been completed. No similar problems in guard training have been identified.
This Circular is considered closed.
78-08, Environmental Qualification of Electrical Equipment -
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This Circular has been superseded by Bulletin 79-01.
78-04, Fire Door Design Deficiency -
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No similar design deficiency was found to exist at ANO.
This Circular is considered closed.
77-16, Dnergency Generasor Trip Lock Features -
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Followup on the licensee's testing procedures remains open. This Circular is considered open.
77-14, Separation of Contaminatod Water System -
.
The licensee's review indicates that there is double check valve protection to preclude cross connecting of contam-inated/non-contaminated systems. This Circular is cor.sidered closed.
2228 349
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77-06, Effects of Hydraulic Fluid on Electrical Cable -
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Licensee's review indicates no safety-related cables W
in the vicinity of the turbine's EHC system. This
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Circular is considered closed.
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There were no items of noncompliance or deviations identified during
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the inspector's review of Balletins and Circulars.
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15.
Unresolved Items (Units 1 and 2)
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Unresolved items are matters about which more information is required
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deviations. There were four unresolved items identified during this inspection.
(Deta#1s, paragraphs 4, 5 and 11)
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16.
Exit Meetings (Units 1 and 2)
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Exit meetings were conducted on February 16 and 23, and March 2 and 9,
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1979 with Mr. J. P. O'Hanlon (Plant Manager) and other members of the AP&L staff; and on March 16, 1979 with B. A. Terwilliger (Operations
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and Maintenance Manager) and other members of the AP&L staff.
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