IR 05000286/1982007
| ML20033D821 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 06/01/1982 |
| From: | Baunack W, Foley T, Kenny T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20033D820 | List: |
| References | |
| 50-286-82-07, NUDOCS 8206250244 | |
| Download: ML20033D821 (11) | |
Text
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U. S. NUCLEAR REGULATORY.CO W!$580R I
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REGION 1 a --
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Report No. 50286/82-07
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Docket No. 50 266
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License No. DPR.64 Priority Category i
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Licensee: Power Authority of the State of New York
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10 Col mbus Circle
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New Yopk. New York 10019
Facility Name: Indian Point Nuclear Generating Station. Unit 3 inspection att Buchanan. New York Inspection conducted:
ri,1.1982 to May 15.1982
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Inspectors:
S I A7 M T. Foley, 5entor' Resident Inspector
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T. J. Kenny Res' dent Inspec
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W. Baunack. Acting Chief. ion of Project Indian Point tete l
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Resident Section. Divis I [-
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and Resident Programs q f,.
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Inspection Sunnary:
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Inspections on April :,6.1982_ to May :,5.1982 (Int 3ectica Report 50 21 6/82-07)
Areas Enspected: Rousine onstte regu' ar and backs strt inspections erslant operat' ons including shift logs and records; licensee action on previous in-spection findingst plant tours surveillances sedifications to batteryjchargersg
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review of sonth y reportsu followup on IE Bulletinst review of Personnel Quali-fications: and licensee p'ans for coping with a potential strike.
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spection involved 103 inspector hours by the resident inspectors.
Resultst Of the eight amas inspected, no violations were identified The Information en this nano it d-d ta ha anneeneinte far Puhite n elaeuca Fursuant to 10 CFR 73.21
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This report details contains M' '
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DETAILS
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Persons Contacted M. Albright, Instrument and Control Superintendent
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J. Brons, Resident Manager
J. Dube, Security and Safety Supervisor D. Halama Q.A. Superintendent
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W. Hamlin, Assistant to the Resident Manager l
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i W. Jostger, Superintendent of Power
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l J. Perrotta, Radiological and Environmental Services Superintendent
i S. Munoz, Technical Services-Supervisor i
E. Tag 11amonti, Operations Superintendent J. Vignola, Maintenance Superintendent l
The inspector also interviewed and observed other licensee employees in-cluding members of the operations, health physics, technical services, main-i tenance, and security staffs.
Licensee Actions on Previous Inspection Findings
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(Closed) Deficiency (50-286/79-30-05) Improper labeling of radioactive
material container: The inspector reviewed procedure HPP-9.1 and 9.2 which I
were changed to address the inspectors' concerns. The inspector also re-i l
viewed RE-HPI-9.11 (Procedure for shipment of radioactive materials) which l
supercedes HPP-9.1 and 9.2.
The new pmcedure contains the necessary in-structions for the proper labeling of containers.
(closed) Inspector follow item (50-286/80-21-03) Review of Surveillance test 3PT-Q7, perfomed 12/24/80. The inspector reviewed this, which was perfomed using the latest revision, and found it satisfactory.
(Closed)UnresolvedItem(50-286/81-18-01) Evaluation of air switches used in the battery chargers: The inspector reviewed design change 82-3-030 BC and verified the addition of an alam versus a battery charger trip. See Section 5 of this report for details.
(Closed) Violation (50-286/82-03-01) Failu m to control documents in accor-dance with adninistrative procedures: The inspector reviewed and verified the action taken by the licensee in their letter of April 28, 1982. The inspector found this action satisfactory.
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3.
' Plant Tour f
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Nomal and backshift inspections were conducted during routine entries into the protected area of the plant, including the control room PAB,
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fuel building, and containment. During the inspection activities discussions were held with operators technicians (HP & I&C),
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mechanics, foremen, supervisors, and plant management. The purpose
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of the inspection was to affim the licensee's conmiitments and
compliance with 10 CFR, Technical Specifications, and Administrative
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Procedures.
Particular attention was directed in the following amas:
l Instrumentation and recorder traces for abnomalities;
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l Proper control room and shift manning; l
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Proper use of pmcedures;
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Review of logs to obtain plant conditions; f
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i Verification of proper radiologically controlled amas and
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access points;
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Verification of surveillance testing for timely completion;
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Verification of safety related tagouts;
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Plant housekeeping and cleanliness;
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That protected area access controls were in confomance with
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the security plan, including sufficient guards to perfom duties.
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and that selected gates and doors were closed and locked, i
Selected liquid and gaseous samples to verify confomance with
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regulatory requirements prior to release; and,
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Boric acid samples to confim pmper boric acid level for plant
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shutdown conditions.
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B.
During the inspection, the inspector reviewed the following pmcedums, documents, or tests:
Radioactive hste Release Pemit (liquid)
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Various shift turnover checklists
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Security Station Logs and Radio Checks
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Jumper Log
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ANSI N 18.1
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PASNY Quality Assurance Manual
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FP-INT-R3 Refueling Procedure
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TOP-32 Rev. O Addendum to Contairment Integrity l
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SOP-CB-1 Containment Integrity
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Selected Tagouts
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Selected REA's (Radiation Exposure Authorizations)
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Findings:
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(1) The inspector noted the following On Ap(S/G) was not barricaded.the secondary side manway access to #33 Stea ril 30,1982, l
tor The inspector measured the hi
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j radiation area inside the S/G to be 250 m1111mm per hour a>ghest accessible proximately
one foot from the feed ring. The inspector also observed tiat No. 31 S/G
manway access was not barricaded. A radiation posting on the sides of the
S/G manway access point indicated, that the interior was a High Radiation
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area with a general ama meding of 300 m1111mm per hour. The sign re-j quired a Radiation Exposure Authorization (REA) prior to entry.
r The inspector also noted four additional access poin'ts to the High Radia-tion area inside the biological shield wall on the 95 foot level that were i
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not barricaded. Additional observation revealed that the loop amas around
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the reactor coolant pumps contained numerous High Radiation areas. The li-consee had barricaded, posted and saintained control of these areas inside
the biological shield wall from all access points with the exception of the four reactor coolant pump access points fmm the 95 foot level. The inspector had discussions with a Health Physics technician who inferred that there was some question within their department concernin barricades were required for access points to the loop areas. g whether He also
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inferred that the entire containment was considemd a High Radiation ama,
and the necessary controls were established at the entrance to the con-
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tainment.
The inspector reviewed the established controls at the containment entrance
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and compared them to the Technical Specification (TS) requimments.
The containment door was not barricaded, and individuals entering the contain-ment are not provided with a self-integrating radiation detecting device
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or a Health Ptysics technician as mquired by TS, however, these controls am established around the biological shield wall, i
The inspector discussed the method in which the licensee controls High Radiation areas inside the containment with the Radiological Superintendent.
The licensee's repmsentative maffimed that barricading High Radiation areas inside the containment was not necessary because controls were -
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established at the containment entrance.
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The inspector discussed this operating philosophy with NRC regional-
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i specialist inspectors, and then, with the >1 ant manager, and subsequent-l ly, with the radiological superintendent ww stated that in the future
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all High Radiation areas, regardless of location, would be barricaded.
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During power operation controls at the containment access are adequate.
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l However, the acceptability of controlling high radiation areas during.
shutdown, from the access to the containment, does not totally address
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I within the containment.
j Due to availability of knowledgeable Health Physics technicians within the containment, the ins >ector concludes that sufficient controls were
l established to pmtect tw health and safety of individuals and, during i
subsequent inspections of the containment, the inspector, noted that all
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i high radiation areas were properly barricaded.
Discussion with Health
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l Physics technicians confimed the licensee is properly contmiling High Radiation areas in accordance with Technical Specifications.
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(2) Refueling
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preparations, prior to the
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The inspector conducted a review of refuelinkons with the Supervisor in movement of fuel.
The inspector had discuss
charge concerning the need to keep loose objects outside of the dedicated area roped off for the refueling activities. The Su>ervisor pointed out the Q.A. representative whose task was.to record worcers and materials in and out of the area. The inspector witnessed the removal of three
fuel elements and the transport of these elements to the fuel building.
The inspector also witnessed two new fuel elements being placed into.
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the core.
From the contml room the inspector reviewed the procedure.
for, and witnessed' controls and a,ctivities associated with the addition of two more elements into the com. The inspector also confirmed that a one over M plot was being utilized as required by the procedure.
The inspector conducted an audit of containment-integrity, using the pm-
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cedums delineated in Section 3 of this mport.
No violations were identi-fied. During the replacement of the teactor vessel-head, a rod drive shaft was bent aparoximately 150 The licensee un16tched all the contml rods, l
including tw bent one, without any aroblems.
The upper internals wem removed, and the fuel element with tw control rod in question was removed l
from the core for examination. At the Rod Control Change Station, the
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control red was mmoved from the element.
Examination by television video taping was perfomed on three sides of the element,- and the control rod.
No damage had occurnd. The element was mplaced, and the reactor was
reassembled without further incidents. The bent rod drive shaft was
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mplaced with a spare drive shaft.
The control rods will undergo exten-sive testing during startup from refueling and prior to criticality.
No violations were identified.
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(3) Prompt Report l
The licensee made a pmapt report to the conmission, identifying Pressure l
Transmitters PT 456, 457 and 474 wem out of specification in the non-
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conservative direction. This was discovered during the perfomance of i
Surveillance Test 3PC-R4, " Pressurizer Pressure Calibration." The in-
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spector reviewed engineering analysis that detemined the reactor trip
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signal would have caused a mactor trip at 1797 ps g which is 3 psig
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be ow the Technical Specification limit of 1800 ps The cause of the i
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transmitters being out of calibration has been attr buted to instrument t
drift.
The licensee is further evaluating the cause for instrument drift..
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l No violations were identified.
j (4) ~ Update on Steam Generator Metallurgical Problems f
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(a) Steam Generator Tubes f
The Eddy Current Test program has been completed in,both the hot
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and cold legs of steam generators S/G Nos.-32 and 33. Three tubes
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were removed from No. 33 S/G to be analyzed; two tubes from the cold
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leg and one tube from the hot leg.
One of.the tubes pulled. (Row 1g..
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i Column 47) was the leaking tube, which caused the plant shutdown.
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The results of the analysis of tube degradation have not been re-t viewed by the ins >ector at this time. The vacancies created by the
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removal of the tu >es have been repaired by plugging. A repair for l
the degradation, of the tubes, in the cold leg has not been formally
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addressed by the licensee, at this time, but they are exploring the-l possibility of sleeving. These results will be prior to commencement.of any repair activities. presented to NTR
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(b) Steam Generator Girth Welds The nondestructive testing (NDT) has been completed on #31, 32-and 34 S/G's, and is in pmgress on #33 S/G. All generators exhibit the same internal cracking in the girth welds. A boat sasple has been removed from #31 S/G and analyzed. The results am preliminary, but indicate the possibility of improper heat treatment during the
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fabrication of the girth weld. The primary responsibility for tracking, evaluating and concurring in licensee actions regarding the problems associated with the girth weld, has been transferred from Region I to NRR. The licensee is currently required to obtain NRC pemission prior to startup, after providing an analysis of the problems associated.with the girth welds.'
No violations were identified.
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4.
Surveillance
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I A.
The inspector obsened portions of four smveillance activities being i
conducted on safety related equipment to ascertein the following:
That test instrumentation was properly calibrated; i
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That the redundant system or component was operable;
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t That properly approved procedures were used by qualified jl
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personnel; and, i
That the acceptance criteria was met.
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l Tests observed:
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- 3PT M 31 Instrument Air
- 3PT M 49 Diesel Generator Battery
- 3PT Q 17 Sampling Valves
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- 3PT Q 24 Containment Spray Discharge Valves j
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t No violations were identified.
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The inspector conducted an indepth myiew of suneillance activities i'
to ascertain the following:
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That the conditions listed in "A" above were met;
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t That the test data was accurate and complete;
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That pmper reviews, by the licensee, had been conducted;
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That the results of the tests met Technical Specification i
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mquirements; and.
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That the testing was done within the required surveillance
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Tests reviewed:
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3PT R77 Full Flow Thru Valves 867 A & B
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3PT Q30
- Hydrogen Recombiner Containment Isolation Valves l
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3PT R38 Shock Suppressors Functional Test
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Findings:
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The inspector witnessed the Aysical testing of a snubber on the Bergin Patterson testing machine. The licensee has purchased a chart recorder,
which is now utilized during the testing of tie snubbers.
The recorder i
provides a printout which more clearly definas lockup and bleed rates.
The inspector also reviewed the test results and recorder traces. for
the following snubbers.
All were satisfactorily tested.
Snubber Number fi'L'ocation**
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RCR-344-4A-H 123' top. of pressurizar RCR 25-H 70' 34 RCP and shield wall
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I RCR 778-2-H 66' between 32 $/G & Pitshield on RTD manifold l
RCR-82-2 51' between 32 $/G & 32 RCP
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CHR 17C-14-H 47' COL #2 bottom of spiral staircase
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ACR-10-15' PAB-RHR line for 32 pump'
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ACR-216-H 15' PAB 31 RHR planp room
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CHR 695-11
,43' PAB weste holdup tank area in overhead MSR-1-2-H 63' AFW B1dg. below grating near MSR 3-2 MSR-2-1 77' AFW Bldg. south end 31 steam line
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No violations were identified.
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50 Modification to Battery Chargers The inspector reviewed Modification 82-03-030 BC, " Improvements to Battery i
Chargers Nos. 31, 32, 33 and 34."
The inspector also verified the following:
The design change was reviewed and approved in accordance with
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administrative procedure;
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The design change was contmiled by established procedures;
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The revision drawings were properly issued in accordance with
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adninistrative procedure; and, The units have been tested in accordance with approved procedures.
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The modification consisted of:
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The removal of the loss of air flow relay (63JAX) from the trip
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circuitry and the addition of this relay to the comon alam on
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the Supervisory Annunciator System for Battery Charger Numbers
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31 and 32;
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The installation of acknowledge switches for each individual alam l
on a battery charger that actuates the comon alann on the Super-
visory Annunciator for Battery Charger Numbers 31, 32, 33, and 34;
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The removal of the equalize charge timing relay and associated re-c.
lays and the installation of a key operated selector switch for l
controlling operation mode of the charger;
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The relocation of the D.C. Voltage Adjusting Potentiometers to
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facilitate access to these potentiometers without requiring the
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opening of the battery charger cabinet door on Battery Charger Nanbers 31 and 32; and, e.
The replacement of the charge / discharge switch with a key operated selector switch on Battery Charger Numbers 33 and 34.
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No violation' were identified.
s 6.
Review of Monthly Report
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A.
Monthly Operatino Report The Monthly Operating Report for March and April,1982 were reviewed.
The review included an examination of selected maintenance work re-quests, and an examination of significant occurrence reports to as-certain that the sumary of operating experience was properly documented.
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Findings:
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The inspector verified through record reviews and observations of l
maintenance in progress that:
The corrective action was adequate for resolution of the
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identified items; and,
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The Operating Report included the requirements of. TS 6.9.1.6.
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l The inspector has no further questions relating to the reports, f
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Followup on IE Bulletins l
l The inspector reviewed the following IE Bulletins.
In addition to his:
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connents, he ascertained that:
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I The written response was within the time period stated in the
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Bulletin; i
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The written response included the information required to be i
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reported;
The written response includes adequate corrective action connit-
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ments based on the information presented in 'the Bulletin and-l licensee's response;
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The licensee's management forwarded copies of the written response
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The information discussed in the licensee's written response was
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accurate; and,
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The corrective action taken by the licensee was as described in
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the written response.
(Closed)79-BU-02and79-80-02.-Rev.2:PipeSupportbaseplatedesign
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using concrete expansion anchor bolts. These bulletins were first
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inspected during inspection report 79-16, and again in inspection re-port 79-22, when they were closed by the inspector. This inspector
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re-reviewed the bulletins without any additional comment.
(Closed)79-BU-19: Packaging of low-level radwaste for transport and i
(of this report)pector noted while closing out deficiency, that this bulletin was no m. inspector's
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burial. The ins 79-30-05.
tracking system.
Further review found that this item was' inspected-
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during inspection reports 79-30 and 81-07, and closed out.
The in-
spector re-reviewed the bulletin without any additional consent.
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Personnel Qualifications The experience and educational qualifications of principal mobers of the plant staff were verified to be in confomance with the requirements of ANSI N 18.1.
No inadequacies were identified.
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The inspector reviewed the PASNY Quality Assurance Manual, and Administra-l
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tive Procedures to-ascertain that written adninistrative controls wem established that set forth the minima educational and experience qualifi-
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cations for principal staff positions. The inspector dutemined that -
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adninistrative contmls for qualifications were not~ femally doceented
in any procedure or manual. However, the licensee does utilize an " Exempt l l
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Position Description" fem which describes.the educational: and experience l
prerequisites for these positions. -These premquisites meet the require-
f ments of ANSI N 18.1.
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No violations were identified.
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Licensee Plans for Coping With a Potential Strike l
During this inspection period, the inspector became aware of an appmach-
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The Utility Workers of America. Local 1-2 Union.
At present, the cont ml-
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ing expiration date for the.PASNY agreement with Consolidated Edison and
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room NRC licensed operators are Consolidated Edison esployees working for
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PASNY. The expiration of PASNY's agreement could permit conditions to-l
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l exist in which operators may not report to the Unit 3 control mon for l
work. The inspector ascertained that this condition would only effect i
l the control mom NRC licensed personnel.
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The inspector verified management's plans and resource capabilities for_
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copinti with the potential situation in accordance with NRC regulations.
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The 1< censee's capabilities and plans with regard to the aforementioned
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conditions a M adequate.
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