IR 05000313/1975006
| ML19326C591 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 07/02/1975 |
| From: | Donna Anderson, Madsen G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML19326C556 | List: |
| References | |
| 50-313-75-06, 50-313-75-6, NUDOCS 8004230696 | |
| Download: ML19326C591 (8) | |
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U. S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION IV
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IE Inspection Report No. 50-313/75-06 Docket No. 50-313
,3.g Licensee:
Arkansas Power & Light Company License No.: DPR-51 3 ;..; ;.:
Sixth & Pine Screets
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Pine Bluff,. Arkansas 71601 Category C Facility: '
Arkansas Nuclear One, Unit 1 Location:
Russellville, Arkansas Type of License:
B&W, PWR, 2568 Mwt Type of Inspection: Routine, Unannounced
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Dates of Inspection: June 25-27, 1975 s
Dates of Previous. Inspection: June 11-13, 1975 Principal Inspector:
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D. G. Ander' son, Reactor Inspector Date Other Accompanying Personnel: None
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Revieued By:
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- /<' /'7.C C. L. Madsen, Chief, Reactor Construction and Date-Operations Branch
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SUMMARY OF FINDINGS
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I.
Enforcement' Action A.
Violations None identified by the inspector.
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B.
Infractions None identified by the inspector.
C.
Deficiencies Reporting Requirements
'The inspector id'entified that contrary to Section 6.12.3.2 of the (UE Technical Specifications, a written report of an Unusual Event 75/02) was not submitted within the 30-day required period.
fied Enforcement Matters
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_ Licensee Action on Previously Identi II.
The actions taken by the licensee 1,/ to implement the ma d
This item is closed.
III. Design Changes Not inspected.
IV.
Unusual Occurrences 7504-1 - Deviation'in the Design Requirements for Iodine Precipitation G:
During a LOCA This item was identified by the licensee previously and reported to theThe inspector on May 8, 1975 as UE 75/02.27, 1975 and consequently constitutes report was not received until June an item of noncompliance with reporting requirements.
This item remains open.
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1/.' Letter dated 6/6/75, Cavanaugh (AP&L) to Madsen (IE/IV).
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Other Significant Findings-A.-
7504-2
' Fire Stop: Inspection
'The licensee's representative is reviewing material specifications E"iE:
c and drawings for fire stop installation at both ANO-1 and ANO-2.
A~ comprehensive report will be submitted on 7/14/75.
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This item remains open.
B.
7415-1 Cenerator Separation Test at Power
'The' licensee performed the generator separation test from full power. The reactor did not trip during the test and all test
. objectives were met.
This item is closed.
C.
7414-7-Reactor Building Spray Line Cracks
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The licensee is performing a leak inspection on a once per shift basis.
A final report ccncerning this item will be submitted by the licensee's representative in July 1975.
This item remains open.
D.
'7504-3 Seismic Hydraulic Shock and Sway Suppressors The licensee indicated that periodic surveillance of snubbers will be continued according to written approved procedures.
This item is closed.
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E.
7506-1 Leak in Sensor Line to the Low Pressure Outer Seal Cavity or "B" Reactor Coolant Purp The licensee reported (A0 75-03) a circumferential (1800) crack in a 3/4" line which originates at the low pressure outer seal cavity of
"E" RCP.
The-line was isolated'and replaced.
VI.
Management Exit Interview The inspection findings of June 25-27, 1975 were discussed with Mr. J. W.
. Anderson,'Jr., Plant. Superintendent and.nembers of his staff at the t
conclusion of the. inspection.
The nonccepliance item associated with failure to submit a written report as UE 75/02 within the required 30-day-reporting period was discussed. The following items were discussed during Ethe-cxit-interview:
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1.
Generator Separations Test 2.
Snubber Surveillance 3.
Fire Stops 4.
Building Spray 5.
Semiannual Reporting 6.
Maintenance Activities 7.
A0 75/03 The inspector indicated satisfaction with the progress or completion status associated with each of the above noted items.
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DETAILS
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Persons Contacted Arkansas Power & Light Company (AP&L)
J. W. Anderson, Jr., Plant Superintendent
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G. H. F111er, Assistant Plant Superintendent C. A. Halbert, Technical Support Engineer B. A. Terwilliger, Supervisor of Plant Operations T. Martin, Maintenance Supervisor T. Cogburn, Nuclear Engineer R. G, Carroll, Health Physics Supervisor L. Alexander, Quality ~ Control Inspector C. R. Wright, Quality Control Inspector R. D. Gillespie, Chemist K. W. Cook, Chemist T. E. Tubb, Senior Chemist B. G. Parker, Shift Supervisor T. C. Baker, Chemistry and Environmental Supervisor V. Kinsey, Secretary, PSC D. Trimble, Training Coordinator 2.
7504-2 Fire Stop Inspection The inspector reviewed a letter 2/ which detailed the deficiencies noted during IE Inspection No. 50-313/75-04 and the corrective action recommended by Bechtel.
In particular, a final report will be submitted by Bechtel on 7/14/75 which will contain an evaluation of these deficiencies and recommend action to be taken to correct them. This report will also address itself to design procedures which will be implemented for ANO-1, Unit 2, to control the design and construction of fire stops.
Ir.structions for fire stops will be expanded to include a more comprehensive description of fire stop use, and material appliention requirements, with special emphasis on manufactures recommended procedure for application of flamemastic. A specific requirement will be included for obtaining engineering approval prior to the use of materials not included in the " Notes and Details" section of Drawing E-59.
Also, specific instructions and details will be included for fire stops at wall and floor conduit sleeves. A new detail sheet will also be provided to describe conduit seals (Packing the conduit with inorganic wool covered with flacemastic). With regard to the use of GERTV Silicone Rubber RTV 102 as a seal, Bechtel is presently investigating the use of other noncombustible sealing materials at ANO-1.
This evaluation will also be covered in the final report.
This item remains open.pending review of final report.
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2/lLetterdated6/2/75,E.H. Smith-BechtelPowerCorporationto-W. Cavanaugh III - AP&L.
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7415-1
' Generator Separation Test at Power
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The licensee performed the generator separation test'from 99.24% full power. This test is required as a part of the power escalation test.
program for ANO-1 3/. The purpose of this test was to verify that the unit can accoc=odate a generator load rejection from 100% full power
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without exceeding safety limits. The test is also conducted to establish that the turbine _ generator will not exceed its design speed and that the plant electrical system will perform as designed for this transient test even though the electrical system may be subject to frequencies in excess of 60 hz.
The following Station Operating Procedures were utilized for this test:
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OP 1202.01, Load Rejection b.
-OP 1202.03, Turbine Trip c.
OP 1202.04, Reactor Trip At 1305 on 5/30/75, test number 800.25, Generator Separation at Power,
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was initiated by opening output brea'.ers 5114 and 5118 and subsequently separating the unit 1 generator from the grid. After the initiation of these actions, the reactor ran back to 15% full power automatically as described with the use of manual pressurizer spray, Reactor Coolant system pressure was continuously maintained below RCS pressure and temperature trip set points throughout the test. The auxiliary governor l
acted to maintain turbine speed below the over speed trip set point. The I
caximum turbine speed reached during the test was 1896 rpm (63.2 hz).
The governor control then caused over compensation to approximately 57.1 hz and several smaller oscillations resulted before control at 60 bz
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was established. Generator load dropped and was then maintained at house
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auxiliary load through the auxiliary transformer.
In summary, the
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inspector verified by a review of test results that the reactor did not trip during the transient and that all test objectives were met.
This item is closed.
4.
7504-3 Seiscic Hydraulie Shock and Sway Suppressors The inspector continued the review of this item.
It was noted that during
. the past year at least five job orders have been issued for maintenance or inspection cf snubbers at ANO-1.
The inspections are performed under the guidelines of the following procedure:
OP 1304.84 - Hydraulic Shock Suppression.(approved 4/18/74)
The licensee indicated that periodic surveillance of snubbers will be centinued.
This item is closed-3/
ANO-1, FSAR,.Vcluce III, Section 14.1.2.8.3.
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Leak in a Sensor I*,e'to the Low Pressure Outer Seal Cavity of "B" Coolant Pucp-(AO.7 /03)
The licensee reported previously (6/20/75) a visible crack of 1800 in circumference in a socket weld of a 3/4" line to a pressure transducer.
.The line originates at the low pressure outer seal cavity of
"B" reactor
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coolant pump. The crack was located on the upstream side of valve RRV 6510F and was' isolable..A replacement lire.was fabricated and welded in place of the leaking line.
Full anti-contamination clothing and air packs were worn during these maintenance activities.
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6.
' Attendance at Plant Safety Committee Meeting The inspector attended the 6/25/75 eeeting of the Plant Safety a..
Committee (PSC). The inspector noted that:
(1) The quorum present and membership was as specified in 6.4.1 of the Technical Specifications.
(2) The teeting was conducted according to a previously prepared-and approved agenda, b.
Matters brought before the PSC during this meeting were:
(1) A0 75/03 review.
(2) haview of certain sections of the Emergency Plan.
(3) Procedural review.
The inspector t.ad no comments on this item.
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7.
Condenser Chlorination i
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'The inspector observed the licensee's activities related to the removal of algae fro = the secondary side of the condenser. Grab samples were being taken at the discharge embayment and analyzed for available chlorine residual by treating the samples with Ortho-Tolidine Solution (R-420)
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prior to ceasurerent with a Hellige Coloriteter. The inspector reviewed l
OP 1605 (Part 11) - Detertination of Chlorine (Cceparator Method) to assure that the analysis was being conducted according to written, approved procedures.
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The inspector had no further'co=ments on this item.
5.
Semiannual Reperts
.The-inspector reviewei the s'etiannual report covering the last half of
.3974, along with facilfiy records relating to-events,.ceasurements, maintenance and plant operating history to verify that:
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'InformationrequestedtoberepbrtedbytheTechnicalSpecifications.
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has been reported.
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The report accurately reficcts information documented in facility records.
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Maintenance The inspector reviewed records of plant maintenance activities to verify that:
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The limiting condition 'for operation was met while components or systems were removed from service'for maintenance, b.'
Maintenance activities which require administrative approval were obtained prior to initiating the work.
c.
Maintenance activities were accomplished nsing approved procedures.
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. Maintenance activities were inspected in accordance with the provisions in the licensee's requirements.
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' Quality control records are available for maintenance activities.
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. Maintenance z.ctivities were accomplished by qualified personnel.
10.
Abnormal Occurrences The inspector reviewed A0 75/03 to verify that:
a.
The'cause was identified and the details were clearly reported to
. facility management'and NRC.
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