IR 05000313/1977011
| ML19320A112 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 07/28/1977 |
| From: | Dickerson M, Madseng G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML19320A109 | List: |
| References | |
| 50-313-77-11, NUDOCS 8004140715 | |
| Download: ML19320A112 (7) | |
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I U. S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION IV
Report No. 50-313/77-11 Decket No. 50-313 License No. DPR-51
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Licensee:
Arkansas Power & Light Company Sixth & Pine Streets Pine Bluff, Arkansas 71601 Facility Name: Arkansas Nuclear One, Unit 1 Inspection At: Arkansas Nuclear One Site, Russellville, Arkansas Inspection Conducted: July 19-22,1977 Inspector:
$ 97. A >. /. 0 4 _ 4 w 7/zg/77 M. W. Dickerson, Reactor Inspector Date
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Other Accompanying Personnel: None Approved By:
[M,C 7/,2 f/77
'G. L. Madsen, Chief, Reactor Operations and Date Nuclear Support Branch Inspection Summary Inspection on July 19-22,1977 (Report No. 50-313/77-11)
Areas Inspected: Routine, Unannounced inspection of calibration (TS Required); Calibration (Non-TS Required); Review and Audits; follow-up on inspector identified and unresolved problems; follow-up on items of noncompliance; and tour of plant areas. The irispection involved 26 inspector-hours on site by one NRC inspector.
Results: No items of noncompliance were identified.
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DETAILS
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Persons Contacted
- J. W. Anderson, Jr., Plant Superintendent B. A. Terwilliger, Supervisor Plant Operations J. Robertson, Assistant Operations Supervisor
- T. M. Martin, Supervisor Plant Maintenance
- R. T. Elder, Assistant In-trumentation & Controls Supervisor J. Lowman, Assistant Instrumentation & Controls Supervisor S. J. McWilliams, Planning & Scheduling Coordinator
- L. Alexander, Quality Control Engineer
- S. S. Strasner, Quality Control Inspector
- B. L. Beta, Qua'ity Assurance Engineer I. J. Bccler, Assistant Plant Supervisor Maintenance
- P. Rogers, Reactor Engineer
- D. W. Bullington, Reactor Technician T. Templeman, Shift Supervisor C. Zimmennan, Assistant Plant Operator
- Attended Exit Interview 2.
Licensee Action on Previous Inspection Findings (Closed) Noncompliance (7615) Inadequate drawing control.
Revised drawing control procedure No. 1004.23, " Drawing Control," Revision 3, was approved for use on June 20, 1977. This matter is considered resolved.
(Closed) Noncompliance (7709-1) Failure to follow procedures. The inspector reviewed the licensee's corrective action described in their reply dated July 1, 1977.
Included in the corrective action was a memorandum from the Supervisor Operations to all operators which reiterated the require-ment of procedure 1005.01 to complete all logs and records in adequate detail. This matter is considered resolved.
(Closed) Noncompliance (7709-2)Procedurenotupdated.
The inspector reviewed procedure No.1302, " Periodic Calibration of Incore Detectors,"
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Revision 0, dated June 15,.1977, and the licensee's corrective action described in their reply dated July 1,1977.
This matter is considered resolved.
(0 pen) Unresolved Item (7617) Procedural conflict between Quality Assurance
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Procedure 1004.01 and Nuclear Services Procedure NSP-5. A draft of procedure 1004.01 has been completed.
Resolution of this item is still expected by August 15, 1977.
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-3-(Closed) Unresolved Item (7602) Procedural requirements not clear.
The licensee has revised Procedure No. 1401.08, "CROM Removal and
l Installation," to provide clarification of procedural require-ments. Revision 0 of the procedure was approved for use May 27, 1977. This matter is considered resolved.
(Closed) Unresolved Item (77-03) Use of ASME Code Case 1698. The inspector reviewed the April 13, 1977 letter from NRR to AP&L and the April 25, 1977 letter from AP&L to NRR committing to applying ASME Code 1698 with additional provisions. The correspondence provides the additional information required to resolve the item.
This item is considered closed.
.(Closed) Unresolved Item (77-03) Halogen and sulfur content of UT
couplant. The inspector reviewed the letter dated February 22,
1977 from Harry Miller Corporation providing additional information on the testing and certification of theHamber UT couplant with
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regard to halogen and sulfur content.
The correspondence provides the additional information required to resolve the item. This item is considered closed.
(Closed) Unresolved Item (7709-1) Difference in calculation of linear heat generation rates. The licensee informed the inspector O
that incorrect control rod position inputs resulted in the difference in linear heat generation rates. This has been corrected and the plant computer, the Nova computer and hand calculations, now agree. This matter is considered resolved.
(Closed) Unresolved Item (7709-2) Failed self powered neutron detector inputs. Corrections to the inputs on both computers have been made (bad multiplexer cards) and a review indicates that a failed detector is now correctly indicated by each of the computers.
Procedure 1302.15, " Core Performance Monitoring and Fuel Management Data," Revision 0, was approved on June 16, 1977 and provides for comparison of the Nova and plant computer output data. This matter is considered resolved.
(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 has indicated that a procedure will be prepared to provide for this control.
3.
Review and Audits The inspector reviewed the licensee's program and records of review conducted by the Plant Safety Comittee and the Safety Review Conmittee.
Included were reviews required to be completed by the Technical Specifications. A review of audits was not required at
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this time since they were reviewed during the previous inspection.
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-4-The records reviewed by the inspector were as follows:
PSC Minutes 11/76 - 5/12/77 SRC Minutes 11/76 - 6/7/77 No items of noncompliance or deviations were identified.
4.
Calibration The inspector reviewed the licensee's procedures and records relative to the calibration of components, required by the Technical Specifi-cations as listed below:
a.
1304.18 - Boric Acid Addition Tank Level and Temperature
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Instrumentation Surveillance Test, Rev.1, April 11,1974, Calibrated February 8,1977 for LT-1604 and T.T 1604.
b.
1304.32 - Power Range Linear Amplifier Calibration at Power, Rev. O, PC #2, April 12, 1977, Calibrated July 15, 1977.
c.
1304.90 - Off-Site Power Undervoltage and Protective Relaying
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Interlocks and Circuitry, Rev. 3, TC #3, December 13, 1976,
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Calibrated March 9, 1977.
d.
1304.52 - Engineered Safeguards Activation System Analog Channel No.1 Calibration, Rev. O, PC #1, February 22, 1977, Calibrated February 22, 1977.
e.
1304.13 - High and Low Pressure Injection Flow Instrumentation Surveillance Test, Rev. 2, February 15, 1977, calibrated February 22, 1977.
f.
1304.47 - Control Rod Drive System Calibration and Functional Test, Rev.1, PC #1, March 1,1977, calibrated March 17, 1977.
During the review of records relative to the calibration of off-site power relays it was apparent that Procedure No. 1304.90 does not require that information on the "as-found" as well as the "as-left"
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condition be recorded. Although additional data to support the calibrations was available, it was not required by the procedure.
The licensee indicated that the procedure would be revised by October 1,1977 to provide a requirement for this information.
This item will remain unresolved and is designatad 7711-1.
The inspector had no further questions in this area.
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Calibration - Not T/S Specified The inspector reviewed those procedures and records for calibration of components associated with safety related systems or functions which are not specified in the Technical Specifications as requiring calibration, as listed below:
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a.
1302.03 - Periodic Calibration of Incore Detectors, Rev. O, August 30, 1974, Calibrated January 15, 1977.
b.
1304.21 - Condansate Storage Tank Level Instrumentation Periodic Surveillance, Rev. 1, October 14, 1974, Calibrated January 28, 1977 for LIS 4201.
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c.
Diesel Generator "A" Low Level Trip and Alarm, PSL-5270 and PSL 5272, Calibrated December 8,1976.
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d.
Diesel Generator Fuel Tank Level - Local PDIS-5211(A) and PDIS-5212(B), Calibrated November 26, 1976.
e.
Spent Fuel Pool Cooling System, FIT-2000, Calibrated
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September 28, 1976.
f.
Feedwater Flow, FE PDT-2627(A) and 2628(A), Calibrated February 10, 1977 and February 14, 1977.
g.
1304.22 - Pressurizer Level and Temperature Channel Instrr;.catation Surveillance Test, Rev.1, April 18,1974, Calibrated March 16, 1971.
h.
Pump Seal Leakage, PT-6580(A) and PT-6510(A), Calibrated March 8, 1977.
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Circulating Water Pump, TE-3616, calibrated June 30, 1976.
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Analog Input Processing, P-136, Channel B0562, Calibrated -
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undated.
Those instruments noted above for which there is no specific procedure stated are calibrated utilizing procedure 1302.01, " General Process Instrument Calibration Procedure," Rev. 1, approved September 23, 1975, the manufacturers instructions and data sheets.
However, the procedure does not require that manufacturers instructions be utilized, nor does it specify the data sheets may be used for simple calibrations. Moreover, the procedure does not require that acceptance criteria be specified.
Several of the data sheets reviewed were found to have no stated acceptance criteria and one
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was found to have the incorrectly stated string accuracy. These (continued)
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items were discussed with the licensee who indicated that procedure 1302.01-would be revised to provide a definitive pro-cedure, instruction, data sheets and acceptance criteria.
This item will remain unresolved and is designated 7711-2.
The inspector had no further questions in~ this area.
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Circular 76-05
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The Circular requested the licensee to determine if Grinnell Hydraulic Shock Suppressors having a serial number beginning with "B" were installed at ANO-1.
It was detemined by the licensee that all snubbers at ANO-1 were installed prior to November 1974 and that no Grinnell Hydraulic Shock Suppressors having a serial number starting with "B" are installed.
7.
Startup Testing of the New Plant Computer
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The inspector reviewed the specific test results of the licensee's test program for the newly installed computer.
The test was
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composed of data generated for four core burnup cases.
Review of the test data was completed by B&W and AP&L on June 17, 1977.
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The inspector had no further questions in this area.
8.
Cycle 2 Startup Report The inspector reviewed the cycle 2 Startup Report for the period
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ending April ll,1977.
Principal tests were:
a.
Control Rod Drive Trip Time b.
Determination of Critical Boron Concentration
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Determination of Moderator Temperature Coefficient f
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Control Rei Reactivity Worth Measurements e.
Ejected Rod Worth Measurements f.
Core Power Distribution g.
Power Imbalance Detector Correlation h.
Determination of Reactivity Coefficients at Power No items of noncompliance or deviations were identified.
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Unresolved Items
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Unresolved items are matters about which more information is required in order to ascertain whether they are acceptable items, items of noncompliance, or deviations. The following unresolved items were identified during the inspection:
7711-1 Procedure Deficient, paragraph 4 7711-2 Procedure Inadequate, paragraph 5 10.
Exit Interview An exit interview was conducted on July 22, 1977 following completion of the inspection. At the interview the inspector discussed the findings indicated in the paragraphs above. The licensee acknowledged these findings.
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