IR 05000313/1975009
| ML19320A156 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 08/28/1975 |
| From: | Donna Anderson, Madsen G, Rich Smith NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML19320A149 | List: |
| References | |
| 50-313-75-09, 50-313-75-9, NUDOCS 8004140749 | |
| Download: ML19320A156 (10) | |
Text
{{#Wiki_filter:.__ , . . ,- - ' , ( - U. S. NUCLEAR REGULATORY COMMISSION OFFICE.OF INSPECTION AND ENFORCEMENT -
REGION IV
, IE Inspection Report No. 50-313/75-09 Docket No. 50-313 , Licensee: Arkansas Power & Light Company License No.: DPR-51 Sixth & Pine Streets > Pine Bluff, Arkansas Category C Facil'ity: Arkansas Nuclear One, Unit 1 Location: Russellville, Arkansas Type of License: B&W, PWR, 2568 Mwt Type of Inspection: Routine, Unannounced Dates of Inspection: August 18-21, 1975 Dates of Previous Inspection: July 21-24, 1975
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Principal Inspector: [o _., D. G. Anderson, Reactor Inspector Date v \\ h Accompanying Personnel: e u - - R. Smith, Reactor Inspector Date Reviewed By: a 7 hee % [/ [[7.C , 'G. L. Madsen, Chief, Reactor Constr=tien and Date Operations Branch , - 'l .) 8004140 799 .
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' . . . , -2-SUMMARY OF FINDINGS , . A.
Enforcement Action 1.
Items of Noncompliance (a) Violations None identified by the inspector.
(b) Infractions !
None identified by the inspector.
(c) Deficiencies Contrary to Criterion XVII, Appendix B,10 CFR 50, Records of Receiving Inspection of "Q" material do not include the characteristics inspected (DETAILS, paragraph 9) 2.
Deviations None identified by the inspector.
! ! -E.
Licensee Action on Previousiv Identified Enforcement Items D A reply has not yet been received from the licensee on the items of noncompliance identified in the IE Incpection Report No. 50-313/75-07.
' O.
Design Changes JCR 187 Modification to Main Steam and Feed Water Control Valves and Circuitry This design change has been partially accomplished and tested. Further e review of this design change will be accomplished prior to the need date at approximately 250 full power days. This reactor core depletion time is expected to be October 1975.
. D.
Unusual Occurrences The licensee reported an Environmental Occurrence to the inspector during ' the period of the inspection.
(DETAILS, paragraph 4) ' (continued) ' \\v/ . -. -- - , - _ -- -. - -, _ _ _ _..., - -.
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Other Significant Findings ( 1.
' Current' Findings (a) ' Acceptable' Items (1) Abnormal Occurrence Review.
(DETAILS, paragraph 6) J (2) Plant Record Storage and Control.
(DETAILS, paragraph 7) (b) Unresolved Items (1) Control' Panel Annunciators and Alarms.
(DETAILS, paragraph 5) - (c) Items of~ Noncompliance ~ Identified by'the' Licensee None reported.
2.
' Status of Previcusly' Reported Unresolved Items 75-2/6 ' Station and' Switchyard ~ Batteries The inspector reviewad the records relating to switchyard battery surveillance tests. The temperature of every fifth cell was not being measured as required by TS 4.6.2.
The licensee had s previously 1,/ been cited for noncompliance for failure to perform these measurements on station batteries.
Corrective action has ] been initiated by the licensee effective to April 1975. Since~that date all surveillance tests are being performed by ANO-1 personnel and meet the requirements of TS 4.6.2.
This item is closed.
75-2/2 Halon Fire System Test Acceptance The licensee indicated that this test is scheduled to be completed by August 31, 1975.
. i This item remains open pending review of the test results.
F.
Management Interview On August 21, 1975, a meeting was held with plant personnel to identify the scope of the inspection and to summarize the findings of the - inspection. The following individua4s were in attendance: G. H. Miller, Acting Plant Superintendent j .B. A. Tetwilliger, Supervisor, Plant Operations L. Alexander, Quality Control Inspector C. R. Wright, Quality Control Inspector J. Crow, Store Room Supervisor ' T. Martin, Maintenance Supervisor C. A. Halbert, Technical Support Engineer ,t (continued) ) 1/ IE Inspection Report No. 50-313/75-2.
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The inspector described the scope of the inspection and the findings.
The significant items are listed below.
1.
Scope of Inspection 2.
Apparent :!tems of noncompliance. The inspector discussed the ' deficiency summarized above.
3.
Plant Operations and tour observations.
4.
Unre. solved Items 5.
Abnormal Occurrences 6.
IE Bulletin 75-04A
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(continued)
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Persons Contacted , , - Arkansas Power & Light Company (AP&L) J. W. Anderson, Jr., Plant Superintendent G. H. Miller, Assistant. Plant. Superintendent B. A. Terwilliger, Supervisor of Plant Operations J. Robertson, Assistant Supervisor of Plant Operations J. Crow, Store Room Supervisor G. DuPriest, Shift Supervisor L. Alexander, Quality control Inspector C. R. Wright, Quality Control Inspector B. G. Parker, Shift Supervisor V. Kinsey,. Secretary, PSC C. A. Halbert, Technical Support Engineer P. Jones, Instrument and Control Supervisor , R. A. Duvall, Storee Clerk W. L. McDaniel, Stores Clerk T. Martin, Maintenance Supervisor M. Bishop, Administrative Assistant
1.
Plant Status The reactor was operating at 93% FP during the time period encompassed by the inspection.
3.
Cable Spreading Reom ' In his July 29, 1975 letter (Woodward, AP&L to Howard, IE:IV), the licensee committed to placement of a sign on the door of the cable ,. . spreading room (021) which pointed out that no open flames would be allowed in the room. The following sign now is attached to door 021: NO SMOKING OR CARRYING OF LIGHTED MATERIALS
BEYOND THIS POINT
The inspector had no questions concerning this item.
4.
Environmental Occurrence The licensee reported EO 50-313/75-45 to the inspector during the inspection (August 19, 1975). The EO was related to a minor discharge of acmonia in the discharge water from the plant. The licensee repre- , sentative indicated that the follow-up reports would be submitted as required.
The inspector had no. comments on this item.
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Plant Operations J a.
A plant tour of accessible areas was conducted ~and the following ' observations were made: ) (1) Plant process parameters were being monitored and recorded as required and were within TS requirements.
(2) The number of control room personnel on duty met the TS requirements.
(3) Radiation controls were properly established.
(4) Plant housekeeping conditions were in good order.
(5) During the plant tour, no significant fluid leaks, piping vibrations, nor inappropriate settings, etc., on pipe bangers or seismic restraints were noted. However, it was ' noted that a core spray piping hydraulic snubber had a slight hydraulic leak from the oil reservoir. Also, the boric acid mixing tank cover was not in place.
These observations were discussed with the licensee.
b.
Control Panel Annunciators'and Alarms _ During a tour of the control room, the inspector noted three . annunciators operating in che alarm condition. The three annunciators are related to level indication of the borated water storage tank, Sodiitm Hydroxide tank, and the core flood tank. The licensee indicated that since the level annunciator and sensor unit setting is so close to the Technical Specification required limit, slight changes in level result in accuation of the ' alarms and hence lighting of the annunciators. The licensee also , indicated that it is impossible to meet the requirements of . Technical Specification 3.3.4(B) and that a change to that particular Technical Specification has been submitted to DRL (USNRC).
- The licensee further stated that the above noted level annunciators (and in addition the Sodium Thiosulfate tank level annunciator)
have been alarmed for long periods of time since startup of the plant. The inspector addressed the fact that operation with these-level annunciators continuously in the alarmed condition would tend to place more responsibility upon the operator to assure that the Technical Specification required minimum level limit is not reached.
. The inspector indicated that this item is unresolved pending further evaluation.
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Abnormal Occurrences The inspector reviewed A0 75/03, A0 75/04, and A0 75/05'to verify that in each case: a.
The cause was identified, evaluated, and corrective action taken.
b.
The details were clearly reported to the NRC and facility manage-ment as required by the Technical Specifications.
c.
Each report was submitted for distribution and review was performed as required by the Safety Review Committee.
d.
Follow-up action is either completed or in progress.
7., Plant Record Storage'and' Control The inspector verif1ed that the program for the control, storage, retention and and retrieval of records and documents is in conformance I with the requirements of the Technical Specifications. In particular, a.
an index is being maintained for plant records; b.
a distribution procedure is provided; d each record is identified and classified according to number; d c.
d.
for the records reviewed, a procedure for retention, receipt control, storage, and preservation is being followed; records are eas'ly accessible.
i e.
A sampling of the following selected records met the requirements outlined above: ,' 1102.01 Surveillance Records for Reactor Coolant System Leak Test (5/4/75) ' NR 0513 Interuediate Power Recorder Chart (5/28/75 - 6/26/75) , 1304.34 Test / Calibration Records for Incore Detectors (9/26/75 - 7/29/75) j 271.08 Verification Test of Level Indication on once through Steam Generators (7/20/73)
273.36 Pre-operational Test on Auxiliary and Emergency Feedwater System (5/30/74) (continued) b . -- . -- - _
. .. . . , , . -8- . s 400.03 AC Power Systems Energization. Test (5/20/71 - 8/23/73) ~- 1104.36 ~ Emergency Diesel A Test Surveillance (3/1/74 - 11/25/74) NSS and Safeguard, Auxiliary Log (4/1/75 - 6/30/75) , 1104.05 Quarterly Test - Reactor Building Spray Pump (3/3/74 - 11/11/74) The inspector verified that as-built drawings are being maintained and updated as required. The following drawings met these require-ments: - E-560, Bechtel 6600, Main Control Panel, C20 E-202, Bechtel 6600, Pressurizer On-Off Heater Power and Indicator The inspector verified that records of reactor operations and of equipment performance are sufficient to permit review by licensee personnel to detect long term equipment degradation or adverse trends in plant operation that could result in potential technical specification related safety problems.
8.
Reports Pending Review The licensee indicated that several reports are expected to be received from licensee consultants during the last week of August 1975. These s_, reports relate to the following previously documented items: a.
7504-1 Deviation in the Design Requirements for Iodine Precipitation during a LOCA b.
7504-2 Fire Stop Final Review c.
7414-7 Reactor Building Spray Line Cracks The inspection indicated that 'b' above would be reviewed during the next inspection and that 'a' and 'c'. above should be transmitted for review to the Region IV office (IE/NRC).
9.
Procurement . The procurement of safety related equipment and materials was inspected to verify conformance with the requirements of AP&L Quality Assurance Manual-Operations, Section 7 (Control of Purchased Material, Equipment, and Services), and parts of Criteria XIII, KV, and XVII of Appendix B to 10 CFR 50.
The inspector selected the following spare items for inspection: reactor coolant pump parts, control rod drive mechanisms (continued) !t> i . --a
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. ,. . . . .- . - -9- .. {~')N ( with power supplies and position indicator coils, compensated ion '- chamber nuclear detector. The purchase orders for these items were examined for proper approval, records of source, and receiving inspection acceptance testing, and certification data required of the suppliers. The inspector also reviewed AP&L's approved supplier list and compared the vendors of the above equipment to verify an approved supplier.
The inspector reviewed the storage area for segregation, cleanliness, storage, packaging,-and environmental control. The above listed items were adequately identified as acceptable material and were segregated from non-Q items and were traceable to the purchase orders.
A review of the receiving inspection report sheets indicated these inspections of critical components were being inspected, but records did not exist that provided the specific characteristics that were inspected. The lack of documentation of these characteristics is
considered an iten of noncompliance with Criterion XVII of 10 CFR 50, Appendix B, which states, in part, " Inspection and test records shall, , as a minimum. . identify... the type of observation and the . results."
10.
Design, Design Change and Modification a.
Facility records, relative to selected design changes completed p during the previous year starting December 1974, were reviewed t i and discussions relative to these changes were held with the \\.- / licensee. The following areas were examined during this insp3ction: (1) Written safety evaluacions as per 10 CFR 50.59.
, (2) Review and approval of the change pursuant to the Technical Specifications and established QA procedures.
(3) Implementation of the change as required by procedures.
i , (4) Acceptance test records verifying satisfactory performance.
(5) Review and approval of the performance of the modified ' equipment.
(6) Operating procedure, where applicable, to the changes made.
, (7) As-built drawings, changed to reflect the modifications.
' b.
The design changes reviewed were as follows: (1) DCR 187 Modification to Main Steam Stop and Feed Water Control Valves (continued) -s \\ l - J .
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' . .,. , , . . i _10- \\,g (2) DCR 127 Service Water Pump Vent Valve (3) DCR 132 Containment Ventilation for Ducting (4) DCR 272 Radioactive Wastes Surge Tank Level Indication (5) DCR 224 Reactor Coolant Cold Leg Drain Snubber and Vibration Loop Addition (6) DCR'276 Themowells in Main Steam Lines (7) DCR 279 Rupture Disc in Waste Gas Tanks Relief Lines c.
The following summarizes the inspector's findings: . (1) Each of the changes were implemented in accordance with'the established procedures.
(2) The acceptance test records indicate that the acceptance criteria contained in the installation and test procedures were met for each change where required.
. (3) The performance of the modified equipment was reviewed and i approved for each change.
O (4) Reviews of the changes were conducted by the Plant Safety Committee and by the Safety Review Committee where required.
(5) Procedures were revised, where appropriate, to reflect the changes to equipment.
(6) Selected as-built drawings were reviewed for DCR 187, 224 and 272. Drawing sketches were provided in each case to perform the modification; however, the master drawings were not corrected in all cases to identify the modification.
'; The drawings were recently turned over to AP&L from the ' construction Architect-Engineer (AE) and a major plan and updating of drawings is in progress.
. Drawing control and drawing change will be reviewed at a { future inspection.
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