IR 05000313/1977002
| ML19309D772 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 01/27/1977 |
| From: | Dickerson M, Johnson W, Madsen G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML19309D762 | List: |
| References | |
| 50-313-77-02, 50-313-77-2, NUDOCS 8004110662 | |
| Download: ML19309D772 (12) | |
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O U. S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION IV
IE Inspection Report No. 50-313/77-02 Docket NO. 50-313
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Licensee:
Arkansas Power & Light Company License NO. DPR-51 Sixth & Pine Streets Pine Bluff, Arkansas 71601 Category C Facility:
Arkansas Nuclear One, Unit 1 Location:
Russellville, Arkansas Type of Licensee: B&W, PWR, 2568 Mwt Type of Inspection: Routine, Unannounced Dates of Inspection: January 17-21, 1977 Dates of Previous Inspection: December 6, 1976
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Principal Inspector:
. W.
M. W. Dickerson, Reactor Inspector Date Accompanying Inspector:
hI_ Iem r/ay/f 7
.Dgohnson,ReactorInspector Date Reviewed By:
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'G. L. Madsen, Chief, Reactor Operations and Date Nuclear Support Branch
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SUMMARY OF FINDINGS I.
Enforcement Action A.
Violations None B.
Infractions 1.
Contrary to 10 CFR 50, Appendix B, Criterion V and Section 5 of the licensee's approved QA Program:
(a) Maintenance Procedure 1405.01 does not include appropriate acceptance criteria for the daily surveillance checks on the station batteries as required by Quality Control Procedure 1004.12.
(DETAILS, paragraph 5.b(2))
(b) The computer printouts for the Power Range Linear Amp Calibration at Power were not signed as required by Surveillance Test Procedure 1304.32.
(DETAILS, paragraph 5.b(3))
O C.
Deficiencies V
None identified during this inspection.
II.
Licensee's Action on Previously Identified Enforcement Matters 75-07 18/1 Fire Stoos Design Control The installation of fire stops has been completed with the installation on three feed pumps for the startup boiler lines penetrating the startup boiler room walls. This matter is considered resolved.
75-14 A.l.C Procedures Not Approved The corrective action described by the licensee in their letter dated March 1, 1976 has been completed. This matter is considered resolved.
76-17 I.B Failure to Follow Procedure The corrective action described by the licensee in his letter to the NRC dated January 10, 1977 has been reviewed by the inspector.
This matter is considered resolved.
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III.
Design Changes Not inspected.
IV.
Unusual Occurrences None identified during this inspection.
V.
Other Significant Findings A.
Current Findings 1.
Plant Status During the period January 17-21, the power was reduced from s90% to 60% and is expected to be reduced to s40% by January 22, 1977. The power is then expected to remain at s40% until January 27, 1977 when the plant will shutdown for a refueling outage.
2.
Unresolved Items a.
Procedural Requirements Not Clear Several temporary changes to Maintenance Procedure 1401.08 indicate complete substitution of the change when this is apparently not intended. Additionally, the change to Section 4.5.5 is contrary to the requirements contained in Section 5.1.34.
This matter remains unresolved.
(DETAILS, paragraph 2.b)
B.
Status of Previously Reported Unresolved Items 75-14 E.b(2)
Preventive Maintenance Activities Preventive Maintenance Procedure 1005.02, Rev. O, " Preventive Maintenance Control Procedure," was approved December 20, 1976.
This matter is considered resolved.
76-17 V.A.2.a DCR 435 - Cables Placed in "0" Trays The licensee demonstrated that "Q" tray loading was considers; for "Q" trays utilized for routing of cables for DCR 435.
.he loading was determined by review of Raceway Schedules.
7e loadings indicated by the Raceway Schedule were revir. sed by the inspector. This matter is considered resolved.
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-4-76-17 V.A.2.b DCR'445 -' Modifications tc~ Auxiliary and Fuel Handling Crane The Job Order #1239 for the modification of the crane circuitry was available for review by the inspector during this inspection.
This matter is considered resolved.
(DETAILS, paragraph 4)
76-17'V.A.2.c Procedural Conflicts - QA Procedure 1004.01 and
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Modifications necessary to remove the procedural conflicts is presently under corsideration. This matter remains unresolved.
VI.
Management Meeting A.
Entrance Meeting A preinspection meeting was held with Messrs. J. W. Anderson and L. Alexander on January 17, 1977. Mr. Anderson was informed that the following items would be reviewed during the inspection.
1.
Procedures 2.
Preparation for Refueling 3.
Surveillance 4.
Previous Items of Noncompliance 5.
Previous Unresolved Items B.
Exit Meeting At the conclu:; ion of the inspection on January 21, 1977, an exit meeting was held with representatives of the ANO-1 plant staff.
The following individuals were present:
J. W. Anderson, Jr., Plant Superintendent B. A. Terwilliger, Supervisor Plant Operations P. Jones, Instrumentation & Control Supervisor T. H. Gogburn, Nuclear Engineer L. Alexander, Quality Control Engineer
The inspector discussed the following items:
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The noncompliance as a result of failure to follow procedures i
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regarding surveillance activities.
(DETAILS, paragraph 5.b)
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The resolution of previous items of noncompliance.
(Section II of the Summary of Findings)
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The unresolved item regarding Maintenance Procedure 1401.08.
(DETAILS, paragraph 2.b)
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The status of previously identified unresolved items.
(Section V.B of the Summary of Findings)
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-6-DETAILS 1.
Persons Contacted The following individuals, in addition to those listed under the Exit Meeting section of this report, were contacted during this inspection.
Arkansas Power & Light Company (AP&L)
I. J. Butler, Assistant Plant Supervisor Maintenance R. T. Elder, Assistant Instrumentation & Control Supervisor F. B. Foster, Production Engineer T. L. Green, Assistant Training Coordinator D. R. Hamblen, Quality Control Inspector P. W. Jacobs, Production Engineer P. Jones, Instrumentation & Control Supervisor V. Kinsey, Assistant Engineer J. N. Martin, Instrumentation & Control Technician T. M. Martin, Supervisor Plant Maintenance J. Maxwell, Shift Supervisor G. H. Miller, Assistant Plant Superintendent B. G. Parker, Shift Supervisor O
J. Robertson, Assistant Operations Supervisor P. C. Rogers, Reactor Engineer C. Shively, Perfonnance Engineer S. S. Strausner, Quality Control Inspector T. Templeman, Shift Supervisor B. A. Terwilliger, Supervisor Plant Operations 2.
Procedures
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a.
Areas Inspected The inspector reviewed plant procedures to verify that they had been reviewed and approved, that control of changes was in accordance with the Technical Specifications, that Technical Specification revisions have been incorporated into procedural changes, and that the content of the procedures conform to TS requirements.
In addition, the content of the procedures were reviewed for their technical adequacy to control the operation.
The following areas were inspected by selective review of represen-tative procedures in each area:
(1)
Administrative Control 1005.02 Preventive Maintenance Control Procedure, Rev. O, 12/20/76 O
1005.12 Standing Orders, Rev. O, T/C #1, 6/2/75
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(2)
Operating Procedures 1103.06 Reactor Coolant Pump Operation, Rev. 2, T/C #1, 9/7/76
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1104.02 Makeup and Purification System, Rev. 4 T/C #2, 70/15/76
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1104.03 Chemical Addition, Rev. 4, T/C #2, 8/20/76 i
1104.24 Instrument Air System Operation, Rev. 1, 7/29/75 1104.37 Communications System Operating Procedure, Rev. 1
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l 1105.03 Engineered Safeguards Activation System, Rev. O, l
5/11/73
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l 1105.09 Control Rod Drive System, Rev.1, T/C #1, 6/17/74 (3)
Maintenance Procedures 1401.05 RCP Shaft Seal Removal & Installation, Rev. 2
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11/19/76 1401.08 CRDM Removal & Installation, Rev. O, T/C #1, 1/12/76
1406.03 PM Items Done According to Computer Generated
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Checklists, Rev. O, 1/12/77 J.0.1425 ESAS Digital Channel #3 - Test Module. Trouble Shoot and Repair, 5/4/76 J.O. 1610 Disassembly, Repair, Inspect, Reassemble "B" Makeup Pump - Work Plan for Repair / Modification, approved 10/4/76 references B&W Instruction Book
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Other PM Procedures for safety related items are under develop-
ment in accordance with procedures 1005.02 and 1406.03 listed
above.
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Abnormal (Alarm) Condition Procedures The inspector reviewed each of the procedures identified in paragraph 2.a(2) above to determine that abnormal condition procedures have been provided for associated alarms.
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(5)
Emergency Procedures 1202.06 Loss of Reactor Coolant /RC Pressure, Rev. 3, 9/3/75 1202.12 Loss of Instrument Air, Rev. 4,7/29/75 1202.26 Loss of Steam Generator Feed, Rev. 2,7/29/75 1203.03 CRD Malfunction Action, Rev. 3,8/18/75 b.
Findings The inspector's review of the above listed procedures indicated that the procedures are generally acceptable; however, operating procedures 1103.06, 1105.09, 1104.03 and 1104.02 contain references to Operating Procedures 1101.01 (Plant Limits and Precautions) and 110.102 (Set Points).
The latter procedures are currently under development and are required to be complete prior to startup from the refueling outage and are an unresolved item from IE Report 76-05. Additionally, Maintenance Procedure 1401.08,
"CRDM Removal and Installation," Rev. 2, contained temporary changes to section 4.5.4, 4.5.5 and 4.5.6 which indicate a complete O
section change. However, the intent of temporary change #1, approved 1/12/76, does not appear to delete the original sections but appear to change only portions. Moreover, the temporary change to section 4.5.5 and the requirements of section 5.1.34 appear to have conflicting requirements. Section 4.5.5 indicates the use of a "T" handle wrench (Torque has been removed by the change) while section 5.1.34 states that use of a "T handled torque wrench must be used for both loosening and tightening." Section 4.5.5 is a step in loosening bolts.
Section 3.3.1 states that "All interior surfaces of the drive mechanism requires Class A cleanliness per Maintenance Procedure 1401.20." This appears to be an incorrect reference and apparently should reference procedure 1406.02.
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These items, as well as other minor items, were discussed with representatives of the licensee. The apparent problems with
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t Maintenance Procedure 1401.08 will remain as an unresolved item
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The inspector had no additional questions in this area.
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3.
Preparation for Refueling The inspector examined the contents and verified that a procedure is
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available for new fuel receipt and inspection. Approved procedures for fuel transfer, core verifications, recycled fuel inspections and for core reconstitution were not available for review.
However, a
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draft of procedure 1502.04, " Refueling Shuffle" was in the process of being formalized. The procedure was developed on the assumption that l
complete unloading of the fuel will not be necessary. However, a
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decision on whether complete unloading is necessary will not be made
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until after the plant has been shutdown for refueling. The decision will be based upon a B&W study of noise analysis instrumentation to
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determine if a piece of the surveillance specimen holder tubes is still in the reactor vessel and can be located.
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Refueling procedures will be reviewed during the next inspection.
The following procedures were reviewed by the inspector:
1502.01 Refueling Operations - Sequence of Events, Rev. O, 3/17/73 1502.03 Preparation for Refueling, Rev. 2, T/C #4, 5/17/76 1503.02 Fresh Fuel Inspection and Storage,. Rev. O,11/1/72 1506.01 Fuel Handling, Rev. O, T/C #1, 3/30/76 1506.02 Control-Component Handling, Rev. O, 4/7/73 4.
DCR 445 - Modifications to Auxiliary and Fuel Handling Crane During the previous inspection, the licensee could not locate a Job Order i
for modification of the crane circuitry to pemit the 100 ton and 10 ton Auxiliary Crane to lift 125% of design weight without saturation of its reactors. During this inspection the J.O. #1239, dated July 22, 1976, was reviewed by the inspector. However, the licensee informed the inspector that apparently the circuitry for the 10 ton Auxiliary Crane had been modified at some previous time. This had been detemined by inspection of the crane circuitry.
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Review of available documentation indicated that the modification had
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apparently been completed in 1973. However, the Harnischfeger drawings had not been revised to reflect this modification. A handwritten letter from Harnischfeger to Bechtel, dated June 2, 1973, stated, "I have marked 4"
up a print to show what is required in order for auxiliary hoist to pick up 125% capacity test load." The referenced drawing contained the referenced note which stated, "This changes crane to pick up a 125% test load in first step raise.
If change OK let me know so I can make a record chang ~e and update drawing." As indicated previously, changes to the affected drawings were not made.
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-10-The inspector stated that failure to assure that the drawings were reviewed for adequacy was considered an infraction. However, the licensee had discovered the problem and had taken corrective action to have the drawings updated.
This matter is considered closed.
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5.
Surveillance The objective of this inspection effort was to ascertain whether the surveillance of components or equipment associated with safety related i
systems or components is being conducted as required by Technical Specifications and in accordance with approved procedures.
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a.
Scope of Inspection (1)
Surveillance Test procedures The inspector selected twelve surveillance tests required by the Technical Specifications. These were reviewed to verify the following:
(a) That each is covered by properly approved and reviewed procedures.
(b) That the surveillance test procedures included:
Specification of prerequisites and preparations for
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the tests.
Specification of functional tests of instrumentation
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specified for use in conduct of the surveillance.
Aopropriate acceptance criteria.
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Operational checks prior to returning the system to
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service.
(c) That the technical content of the procedures is such that their performance. will result in satisfactory testing of the related systems or components.
i (d) That test results are in conformance with Technical Specifications and procedure requirements and that they have been reviewed by someone other than the tester or
individual directing the test.
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(2)
Surveillance Test Witnessing The inspector witnessed the quarterly surveillance test of a reactor building spray pump.
The following items were verified during the surveillance test:
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-11-(a) The test procedure was approved and verified to be the latest revision.
(b) The test procedure was available and was being used.
(c) Test prerequisites had been met.
(d) The individual performing the surveillance test was qualified in accordance with Technical Specification requirements.
b.
Inspection Findings (1)
The following surveillance tests were reviewed:
Procedure No.
Rev.
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Title / Description
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Date 1102.01 Attachment G
T RCS Leak Test
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1 10/15/76 LPI/DH Pump 34A & Components Quarterly Testing 1104.05 Supplement 3
2 10/15/76 Reactor Building Spray Pump Test 1104.34 Supplement 1
3 7/23/76 Control Room Emergency Ventilation t
Monthly Test
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1104.36 Supplement 1
2 4/23/76 Diesel Generator Monthly Test 1106.06 Supplement 1
3 8/20/76 Electric Emergency Feedwater Pump Test 1107.01 Supplement 1
2 8/13/76 Battery Charger Test 1107.01 Supplement IV
Emergency Lighting Test
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3 5/21/75 Personnel Hatch Pressure Test 1304.32
6 11/11/75 Power Range Linear Amp Calibration at Power j
1304.37
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3 10/76 CRD Trip Breaker Test l
1405.01 Attachment A
2 3/22/76 Station Batteries Daily Check (2)
During his review of Maintenance Procedure 1405.01, Station E,atteries and Switchyard Batteries, the inspector noted that no acceptance criteria were included for the daily surveillance checks on the station batteries.
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-12-Section 4.1 of Revision 0 of Quality Control Procedure 1004.12, Operational Test control, states, "All tests required by this procedure shall be perfonned by approved written procedures specifying the test requirements and acceptance limits."
Criterion V of Appencix B to 10 CFR 50 states in part that,
" Activities affecting quality shall be prescribed by documented instructions, procedures, or drawings... and shall be accomplished in accordance with these inscructions, procedures, or drawings." This requirement is furthsr ampidfied by Section 5 of the licensee's NRC approved Quality Assurance Program which states in part that, " Instructions, procedures and drawings shall be provided as necessary for the control of those activities which affect quality." Section 5.2.4 of this program delineates responsibility for assuring and verifying that activities affecting quality are accomplished in accordance with approved instructions, procedures and drawings.
The licensee's failure to adhere to Quality Control Procedure 1004.12 by not including acceptance limits for the daily surveillance checks on the station batteries in Maintenance O
Procedure 1405.01 is an apparent item of noncompliance with the above requirements.
(3)
During his review of the December 1976, results of the perfomance of Surveillance Test Procedure 1304.32, Power Range Linear Anp Calibration at Power, the inspector noted that not all computer printouts had been signed.
For the tests performed on December 3, 13, 23, 27 and 31, 1976, none of the computer printout sheets were signed. For the tests dated December 6,10,15,17 and 22, 1976, one or more of the computer printout sheets were not signed.
Section 7.1 of Surveillance Test Procedure 1304.32, Revision 0, states that, "All computer printouts shall be identified, signed, dated and attached to this procedure." The licensee's i
failure to follow the surveillance test procedure is an apparent item of noncompliance with Criterion V of Appendix B, 10 CFR 50, discussed in paragraph 5.b(2) of this report.
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