IR 05000313/1979017
| ML19210B959 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 10/02/1979 |
| From: | Johnson W, Spangler R, Westerman T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML19210B954 | List: |
| References | |
| 50-313-79-17, 50-368-79-15, NUDOCS 7911130090 | |
| Download: ML19210B959 (9) | |
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U. S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
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RE'i10N IV
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Report Nos. 50-313/79-17
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50-368/79-15 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: ANO Site, Russellville, Arkansas Inspection Conducted: August 12 through September 8, 1979 Inspectors:
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//T7I W. D. Johnson, Resident Reactor' Inspector Date '
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.' G. Spangler4 Reat' tor Inspector Date f'G. H. Verduzco, React'or In'spector Y
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Date de/2 3 //77 Reviewed By:
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T. F. Westerman, Chief, Reactor Projects Date Section
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Inspection Summary Inspection conducted during period of August 12 through September 8,1979 (Report No. 50-313/79-17)
Areas Inspected: Routine, announced inspection consisting of inspector follow-up of previously identified inspection items, licensee actions taken in response to IE Bulletins, review of unit trip, power coefficient of reactivity, core power distribution liinits, audit program and follow-up 1322 323 7911130 Of C
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on licensee event reports. The inspection involved 91 inspector-hours on-site by three (3) NRC inspectors.
Results: Within the seven (7) ateas inspected, no items of noncompliance were identified.
Inspection conducted during period of August 12 through September 8, 1979 (Report No. 50-368/79-15)
Areas Inspected:
Routine, announced inspection of licensee actions taken in response to IE Bulletins, previously identified inspection items, review of
" Millstone Syndrome" fix, audit program and follow-up on licensee event reports.
The inspection involved 54 inspector-hours on-site by three (3) NRC inspectors.
Results: Within the five (5) areas inspected, no items of rc,ncompliance were identified.
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DETAILS
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Persons Contacted Arkansas Power & Light Company Employees J. P. O'Hanlon, ANO General Manager G. H. Miller, Engineering & Technical Support Manager B. A. Baker, Operations Superintendent T. N. Cogburn, Plant Analysis Superintendent T. Holcomb, Scheduler P. Jones, Maintenance Supervisor B. A. Terwilliger, Operations and Maintenance Manager F. Foster, Plant Administrative Manager R. Elder, I&C Supervisor J. McWilliams, Planning & Scheduling Supervisor D. Trimble, Licensing Manager J. Lamb, Safety and Fire Prevention Coordinator C. Shively, Plant Performance Engineer
.A. Cox, Nuclear Engineer P. Rogers, Nuclear Support Supervisor D. Lomax, Nuclear Engineer B. Bata, QA Engineer 2.
Follow-up on Previoucly Identified Items (Units 1 and 2)
(Closed) Item of Noncompliance (Inspection Report 313/368/79-02, paragraph 4): Failure to follow procedure 1005.02, Control of Preventative Maintenance.
The inspector determined that the licensee appears to be implementing fully the requirements of Revision 1 to Procedure 1005.02 dated July 9, 1979. This completes t'ae review of corrective actions for the above item of noncomplianu.
(Closed) Open Item 313/7813-24 (Inspection Report 78-13, paragraph 5):
The term 10E-9 should be IE-09 in step 6.1.18 of Procedure ?302.03.
A permanent change to Procedure 1302.03 was initiated by the licensee to correct the above.
(0 pen) Open Item 313/7725-34 (Inspection Report 77-25, paragraph 3):
Air flow from the Spent Fuel Pool floor through an adjoining door to the Unit 1 computer room.
During discussions with licensee health physics personnel the inspector found that the reactor auxiliary building does not appear to be normally (with both supply and exhaust fans in operation) at negative pressure 22 325
with respect to the surrounding " clean" areas.
Section 9.7.1 of the Unit 1 FSAR states that the design basis flow path for the HVAC systems is from low activity to high activity areas. A request has been submitted to plant engineering to review and evaluate the HVAC design. This item will remain open pending the results of the engineering review.
(Closed) Open Item 368/7907-01 (Inspection Report 79-07, paragraph 6):
Standing Order 32, Fire Brigade, appeared to be outdated.
The licensee cancelled the outdated standing order on May 21, 1979.
(0 pen) Open Item 368/7909-01 (Inspection Report 79-09, paragraph 8A(1)):
Procedure revisions required.
The licensee has completed the necessary revisions to Procedures 2304.70, 2104.29 and 2102.01 (Category E Valve List) identified as the first, third and fourth items of this open item. The second and fifth items remain open. These involve cross referencing the Category E Valve List of 2102.01 to the valve list attachments of the operating procedures to assure that valves are shown as locked in position on both lists and
. adding a locked open designation to 2HPA-37 and adding 2HPA-38 (locked open) to the valve list for 2104.44.
(Closed) Open Item 313/7909-15; 368/7909-04 (Inspection Report 79-09, paragraph 9A):
Post LOCA status of ECCS pump room doors.
The emergency procedures for Units 1 and 2 have been revised to require isolation of the ECCS pump rooms during initiation of the recirculation phase of LOCA cooling.
(Closed) Open Item 368/7910-01 (Inspection Report 79-10, paragraph 10A):
Required revisions to OP 2202.06.
The licensee has revised this procedure to include the necessary changes identified by this open item.
(Closed) Open Item 368/7910-02 (Inspection Report 79-10, paragraph 10B):
Handling of valve lineups.
The licensee has implemented the requirements of the June 11, 1979, revision of Standing Order 3.
(Closed) Open Item 368/7913-01 (Inspection Report 79-13, paragraph 12):
Power variation during performance of 2.800.01, Appendix W.
The Test Working Group discussed this item during a meeting held the week of August 27, 1979, and concluded that the power variation during this test was of no consequence.
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3.
Review of ANO Unit 1 Trip on August 13, 1979 The inspector reviewed the computer Sequence of Events Record and Plant Alarms and Status Messages for the trip that occurred at 17:49:43.000 seconds on August 13.
The trip occurred when n failed relay in the ANO switchyard actuated the backup generator lockout relay. This relay system opened the generator output breakers and initiated a turbine trip.
A burnt lead in the 125V DC circuit to the turbine lockout relay (286-T)
caus:d an open circuit which prevented this relay from actuating the unit lockout. Eight seconds later the unit lockout actuated when the reactor tripped on high pressure.
The H2 (6.9KV) and the A1 (4.16KV)
buses successfully transferred from the unit auxiliary transformer to Startup Transformer No. 1; however, the H1 and A2 buses did not. The cause of the failure of the H1 and A2 buses to transfer could not be estab-lished. All breakers and associated circuitry functioned normally during plant recovery. Apparently the eight second time delay between the turbine trip and the actuation of the unit lockout in combination with relay actuation and reset times was responsible for this failure.
During this review, the inspector identified the following open items:
The Sequence of Events and the Alarm Status Log both indicate a.
erroneously that a Startup Transformer No. 1 Lockout occurred. The source of this problem should be identified and corrected (0 pen Item 313/'917-01).
b.
Breaker 152-213 is the only breaker on which status information was identified in the Alarm Status Log despite the fact that the electrical schemes for computer input from other breakers such as 152-113 are similiar in design. This should be investigated (0 pen Item 313/7917-02).
4.
Review of " Millstone Syndrome" Fix for Unit 2 The licensee's design change to correct the problem identified as the
" Millstone Syndrome" includes, among other things, the sequencing of safe-guards loads following their actuation regardless of the power supply source for the ESF buses and load shedding of nonessential loads as a function of bus undervoltage. During a previous inspection in this area, the inspector created Open Item 313/7906-02 identifing the requirement to add steps in appropriate surveillance procedures which will test those relay circuits associated with nonessential load shedding and bus isolation on undervoltage. Further review in this area indicates that surveillance procedures do not currently test all of the time delay relays added for load sequencing of the engineered safety features components identified in FSAR Table 8.3.1.
Specifically, the load sequencing of the 4.16 KV equipment is verified during the annual integrated ESF test; however, it does not appear that the time delay relays for the 480 volt system (see FSAR Table 8.3.1) are verified in any existing surveillance test.
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The inspector was able to find documentation that these time delay relays were properly set during preoperational testing. This item will remain as an Open Item (368/7915-01).
5.
Power Coefficient of Reactivity (Unit 1)
The ~nspector reviewed the appropriate steps of Procedures 1302.13, Sequencing of Low Power Physics Tests Following Refueling, and 1302.17, Reactivity Coefficients at Power, to determine:
a.
That prerequisites and initial conditions were met b.
That indicated precautions were observed That the measured values were within the acceptance criteria and c.
appeared correct.
No items of noncompliance or deviation were identified during this review.
6.
-Audit Program (Units 1 and 2)
The inspector examined licensee audit procedures and reports to verify that the audit program has been developed and implemented in confarmance with Regulatory requirements, commitments in the application, and industry guides or standards.
Audits conducted by the Safety Review Committee (SRC) were adequate in scope and frequency to satisfy requirements of Technical Specifications and Topical Report APL-TOP-1A (Revision 4) (Quality Assurance Manual Operation).
SRC Audit Reports conducted on the following dates were examined:
- January 19-20, 1977 (Unit 1)
- July 26-28, 1977 (Unit 1)
- July 19-20, 1978 (Unit 1)
- December 12-15, 1978 (Units 1 and 2)
- June 18-21, 1979 (Units 1 and 2)
The inspector followed-up on a sampling of SRC audit deficiencies, to verify response by cognizant supervisors. This sampling would indicate that audit findings are followed-up and resolved.
A long-range Quality Assurance Program, consistent with Regulatory require-ments, has been developed and implemented. The following Quality Assurance Audits were examined:
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- Documents Retention and Disposition conducted June 4-14, 1979
- Job Orders and Trouble Reports conducted January 21~26, 1979
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Inspection of the QA Audit Finding Report Log and Punch List revealed that while responses to deficiencies were made in a relatively timely manner, many were made in excess of the 30 day guideline of ANSI N45.2.12 (1977). This is an open item.
(313/7917-04; 368/7915-02.)
No items of noncompliance or deviations were identified.
7.
Core Power Distribution Limits (Unit 1)
The inspector reviewed licensee procedures and' records to verify that the plant is being operated within the licensed power distribution limits.
The following documents were reviewed:
- Procedures:
1304.48 Core Power Dist>ibution 1302.15 Core Performance Monitoring and Fuel Management Data Collection 1304.32 Power Range Lineav: Amp Calibration 1304.34 Incore Detector Functional Check and Backup Recorder Calibration
- BAW-10123, Babcock-Wilcox ruclear Applications Software Package
- Computer Printouts of core data collected August 16, 17, and 27, 1979
- Operators Quadrant Tilt and Imbalance Log for July 1979
- Computer Daily Logs for July 1979 Reactor axial power imbalance and quadrant tilt data is recorded by the operator from the plant on-line computer (0LC) on a 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> frequency.
Operator logs indicated that imbalance and tilt valves were maintained within license limits.
Core performance data is collected every 10 EFPD. Various parameters describing core power distribution and thermal characteristics are derived from incore instrumentation by the plant OLC using methods described in BAW 10123. ANO-1 cycle 4 reload data has been incorporated into the computer software and verified by a test case provided by B&W.
Licensed power distribution limits as well as design core thermal limits were maintained.
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Records of two.recent calibr c:,ns of incore detectors, backup recorders, and power range linear amplifier were reviewed. Applicable procedures were followed and acceptable results obtained.
No items of noncompliance or deviations were identified.
8.
Inspector Follow-up on IEB Responses The inspector reviewed documentation and interviewed various licensee personnel to determine that the following IEB requirements and licensee commitments had been accomplished:
IEB 79-06B (Unit 2): The additional commitments of Revision 3 dated August 16, 1979, to the licensee's bulletin response have been implemented. Although the requirement for the operators to use incore thermocoup?es to aid in assessing core conditions has been added to Procedure 2202.06, the operator can access, by computer, only one thermocouple at a time. An Engineering change has been requested to provide a better method of computer access. This will remain as an open item (368/7915-03).
IEB 79-04 (Unit 1 and 2); IEB 79-10 (Units 1 and 2); IEB 79-11 (Units 1 and 2): The information furnished by the licensee in responses indicates no further actions are required.
IEB 79-09: The licensee has in place, for Unit 1, procedures and a preventative maintenarce program for the subject circuit breaker.
However, a maintenance procedure for Unit 2 circuit breakers remains to be written and performed.
Inspector follow-up for this IEB on Unit 2 will continue.
IEB 79-05C and 79-06C (Units 1 and 2): Upon receipt of this bulletin, the inspector verified that the interim short term actions required by item 1 of the bulletin had been accomplished by the licensee. The licensee's response to the other items of this bulletin will be reviewed during a future inspection.
9.
Follow-up Licensee Event Reports (LER's) (Unit 1)
The inspector discussed the disposition and corrective action for the following LERs with the Manager of Operations and Maintenance:
78-08, 78-23, 78-24, 78-25, 78-27, 78-26, 78-28, 78-29, 78-31, 78-32, 79-02, 79-03, 79-04, 79-07, 79-08, 79-10.
No further follow-up for the above events is contemplated at this time.
10.
Follow-up on LER's (Unit 2)
The inspector revieweu the disposition and corrective action for the following LER's:
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,79-19 79-37 79 -2
79-39 79-31 79-40 79-32 79-43 79-35 79-50
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79-36 79-53 79-54 No items of noncompliance or deviations were identified.
11.
Sodium Hydroxide Tank (Unit 2)
While reviewing valve lineup sheets, the inspector observed that valves 2BS-32 and 2B5-34 were open due to the NA0H tank (2T10) being it a recirculation mode. The inspector was informed that frequent recircula-tion of this tank is necessary due to the temperature element for the tank being located below the tank heaters. Without recirculation, the heaters would be energized much of the time. This leads to a possibility of overflcuing the tank since the required level is near the top of the tank. The inspector stated that the licensee should evaluate this apparent design problem.
(0 pen item 368/7915-04.)
12.
Exit Interviews Exit interviews were conducted at the end of various segments of this inspection with Mr. J. P. O'Hanlon (Plant General Manager) and other members of the AP&L staff.
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