IR 05000266/1983023

IE Insp Repts 50-266/83-23 & 50-301/83-22 on 831001-1130.No Noncompliance Noted.Major Areas Inspected:Previous Insp Findings,Operational Safety,Maint,Surveillance,Independent Insp & Plant Trips

ML20083B779
Person / Time
Site:	Point Beach
Issue date:	12/06/1983
From:	Bob Fitzpatrick, Hague R, Jackiw I, Jordan M NRC Office of Inspection & Enforcement (IE Region III)
To:
Shared Package
ML20083B756	List: IR 05000266/1983023
References
NRC-2020-000157 50-266-83-23, 50-301-83-22, NUDOCS 8312210277
Download: ML20083B779 (6)

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U. S. NUCLEAR REGULATORY COMMISSION

REGION III

Reports No. 50-266/83-23(DPRP); 50-301/83-22(DPRP)-

Docket Nos. 50-266; 50-301 Licenses No. DPR-24; DPR-27 Licensee: Wisconsin Electric Power Company 231 West Michigan Milwaukee, WI 53203 Facility Name: Point Beach Nuclear Power Plant Units 1 and 2 Inspection At: Point Beach Site Inspection Conducted: October 1 through November 30, 1983 Inspectors: R. a e /2 73

,, v /1 Date

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B. E. Fit pa rick /2/,/73 Date

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[A Approved By: I. N Jackiv, Chief /2 f3 Proj e t Section 2B Date Inspection Summary Inspection on October i through November 30, 1983 (Reports No. 50-266/83-23

[DPRP]; 50-301/83-22[DPRP])

Areas Inspected: Routine, unannounced inspection by resident inspectors of licensee action on previous inspection findings; operational safety; mainten-ance; surveillance; independent inspection; plant trips; and steam generator replacement activities. The inspection involved a total of 424 inspector-hours onsite by two NRC inspectors including 136 inspector-hours on offshift Results: No items of noncompliance or deviations were identifie PDR ADOCK 05000266 G PDR

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DETAILS 1. Persons Contacted

• J. J. Zach, Manager, PBNP T. J. Koehler, General Superintendent G. J. Maxfield, Superintendent - Operations J. C. Reisenbuechler, Superintendent - Technical Services W. J. Herrman, Superintendent - Maintenance and Construction P. J. Skramstad, Superintendent - Cheitstry and Health Physics

• R. E. Link. Seperintendent - EQR R. S. Bredvad, Health Physicist R. Krukowski, Security Supervisor

• F. A. Flentje, Staff Services Supervisor The inspectors also talked with and interviewed members of the Operations, Maintenance, Health Physics, and Instrument and Control Section *Denotee personnel attending exit interview . Action on Previous Inspection Findings (Closed) Unresolved Item (266/79-01-01(DETI) - Procedure did not reflect commitment to ANSI 18.7-1976: Procedure was revised to reflect commitmen (Closed) Noncompliance (266/82-01-04[DPRP]) - Spent fuel stored adjacent to spent fuel divider wall contrary to technical specificatlons: By letter dated October 5, 1983, NRR approved Amendments 77 and 81 for Units 1 and 2 respectively, modifying the technical specifications to allow storage adjacent to the divider wal (Closed) Noncompliance (301/82-21-01[DPRP]) - Improper shift turnover:

Improved operator awareness to turnover procedures has been apparen (Closed) Noncompliance (266/83-04-02[DPRP]) - Failure to follow contain-ment entrance and exit procedures: Procedure was reviewed, deemed un-necessary, and delete . Operational Safety Verification The inspectors observed control room operations, reviewed applicable logs and conducted discussions with control room operators during the months of October and November. The inspectors verified the operability of selec-ted emergency systems, reviewed tagout records and verified proper return to service of affected components. Tours of the Unit I containment, the auxiliary building, and the turbine buildings were conducted to observe plant equipment conditions, including potential fire hazards, fluid leaks and excessive vibrations, and to verify that maintenance requests had been initiated for equipment in need of maintenance. The inspectors, by obser-vation and direct interviews, verified that the physical security plan was being implemented in accordance with the station security pla _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ ___ J

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The inspectors observed plant housekeeping / cleanliness conditions and verified implementation of radiation protection controls. During the months of October and November, the inspectors walked down the accessible portions of the Emergency Diesel Generating, Auxiliary Feed, and RHR systems to verify operability. The inspectors also witnessed portions of the radioactive waste system controls associated with radwaste shipments and barralin At 10:00 a.m. on October 29, 1983, Unit 2 experienced a turbine runback from 100% to 84%. The runback was caused by a spurious rod drop signal which was generated in the nuclear instrumentation while shifting Instru-ment Bus 2Y101 from its normal to alternate power supply for maintenanc After verification that the rod drop signal was spurious, Unit 2 was returned to 100% powe These reviews and observations were conducted to verify that facility operations were in conformance with the requirements established under technical specifications, 10 CFR, and administrative procedure . Monthly Maintenance Observation Station maintenance activities of safety related systems and components listed below were observed / reviewed to ascertain that they were conducted in accordance with approved procedures, regulatory guides and industry codes or standards, and in conformance with technical specification The following items were considered during this review: the limiting conditions for operation were met while components or systems were removed from service; approvals were obtained prior to initiating the work; acti-vities were accomplished using approved procedures and were inspected as applicable; functional testing and/or calibrations were performed prior to returning components or systems to service; quality control records were maintained; activities were accomplished by qualified personnel; parts and materials used were properly certified; radiological controls were imple-mented; and, fire prevention controls were implemente Work requests were reviewed to determine status of outstanding jobs and to assure that priority is assigned to safety related equipment mainten-ance which may affect system performanc The following maintenance activities were observed / reviewed:

Annual maintenance 4D Diesel Generator Residual heat removal heat exchanger eddy current testing Maintenance of IP10 residual heat removal pump Cleaning and inspection of component cooling water heat exchangers Following completion of maintenance on the 4D Diesel Generator and the residual heat removal systems, the inspectors verified that these systems had been returned to service properl r

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5. Monthly Surveillance Observation The inspectors observed technical specifications required surveillance testing on the 4D Diesel Generator, Unit 2 Safeguards Logic and verified that testing was performed in accordance with adequate procedures, that test instrumentation was calibrated, that limiting conditions for opera-tion were met, that removal and restoration of the affected components were accomplished, that test results conformed with technical specifica-tions and procedure requirements and were reviewed by personnel other than the individual directing the test, and that any deficiencies identified during the testing were properly reviewed and resolved by appropriate management personne The inspectors also witnessed portions of the following test activities:

inservice testing of service water pumps, containment spray valves and pumps, and the steam driven auxiliary flood pump . Independent Inspection 100% coverage of spent fuel shipments continued during the inspection perio Interviews with the escorts and independent verification of licensee surveys continue to disclose no problem inspector-hours were expended during this effor The-licensee performed 100% visual inspection of all fuel assemblies from i the Unit 1 core, with the following results: assemblies had one rodlet with cladding breaches, one had the top end cap missing with the retaining spring exposed, two had what appeared to be bulges in the cladding that opened, the other two appeared to have cracks. All of the assemblies are scheduled for reuse in the core.

j assemblies had minor grid strap damage (ranging from scraps to

minor tears). 15 of these assemblies are scheduled for reuse in the core.

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fuel assemblies contained metallic foreign objects that appear to l

be chips, machining shavings, and wires. The licensee intends to l remove the objects that are retrievable from the 20 assemblies sched-

! uled for reuse in the core. The licensee has requested assistance from Westinghouse on resolution of the above visual examination re-

, sults. The licensee also intends to do 100% fuel sipping inspection

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on the assemblies to be returned to the Unit I core.

l This is an open item (266/83-23-01).

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. Plant Trips Following the Unit 2 plant trip at 6:17 a.m. on October 11, 1983 due to a loss of the red instrument bus, the inspectors ascertained the status of the reactor and safety systems by observation of control room indicators and discussions with licensee personnel concerning plant parameters, emer-gency system status and reactor coolant chemistry. The inspectors verified the establishment of proper communications and reviewed the corrective actions taken by the license All systems responded as expected, Unit 2 was made critical at 8:49 and subsequently tripped from 8% power at 10:07 a.m. on low S/G level while shifting from manual to automatic feed water control. The unit was back on line at 11:58 a.m. October 1 . Steam Generator Replacement Activities Unit I was taken off line at 3:20 a.m. on October 1, 1983, to commence the steam generator replacement outage. The reactor was defueled and the upper internals and reactor vessel head reinstalled by October 10. During the week of October 10, the containment was turned over to Westinghouse and Morrison-Knudsen and preliminary work was begun. This included con-struction of a staging area on elevation 21' of containment, removal of insulation from the steam genereators, removal of shield walls on both steam generator cubicles, and construction of bridgework over the reactor vessel cavit During the week of October 17, the bridgework over the reactor vessel cavity was completed, installation of components to upgrade the polar crane commenced, the steam and feed lines for both generators were cut, and weld preparations on the new steam generator lower assembly nozzles were begun. During the rest of the month, preparations were made to cut the hot and cold leg main coolant piping. These preparations included construction of primary and secondary enclosures with multiple ventilation systems to provide progressively lower pressure areas. While making the hot leg cuts on October 31 and November 3, increased containment atmos-(

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phere airborne activity required temporary precautionary containment evacuations. These events were the subject of PNO-III-83-112 and special Inspection Reports No. 50-266/83-11; 50-301/83-1 On November 2, the "A" steam generator steam drum girth weld was cut and on November 5, the "B" steam generator steam drum girth weld was cu On November 11 the first load testing of the modified polar crane com-

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menced. During maneuvers with a 100 ton test weight, problems with the lower pulley blocks prevented completion of the tes Inspection of the

, pulley blocks disclosed bearing and shaft failures. The bearings and j shafts were replaced and a second load test was commenced on November 13.

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During this test the 100 ton lift was satisfactory; however, the 253 ton l lift caused the same bearing and shaft damage experienced in the earlier tes In addition, there was also damage to the pulleys associated with the trolley. At this point manufacturer representatives were brought in to resolve the problem.

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In the meantime, an engineering evaluation was undertaken to determine if the originally installed polar crane which was rated at 100 tons could be used to lift the steam drum upper assemblies which weigh 125 tons, taking into consideration the installed control support pillar modificatio This evaluation was completed and the first steam drum upper assembly was removed and placed in its storage / modification stand on November 15. The second upper assembly was removed later in the week. Both were accom-plished without incident and moisture separator modification work pro-gressed throughout the remainder of the mont The resolution on the replacement polar crane was that the cabling was improperly strung over the pulleys, causing unequal loading on the bear-ings. New pulley blocks were delivered to the site, the trolley pulleys were repaired, and the cabling restrung. A successful load test was completed on November 2 The "A" lower assembly was removed from con-tainment and transported to the storage facility on November 26 and the

"B" lower assembly was removed from containment and transferred to the storage facility on November 27. The first new lower assembly is sched-uled to be brought into containment on December Despite the problems with the crane and the need to reschedule some work, it appears that the outage is running a couple of days ahead of the critical pat . Exit Interview i

The inspector met with licensee representatives (denoted in Paragraph 1) throughout the month and at the conclusion of the inspection period, and summarized the scope and findings of the inspection activities. The licensee acknowledged the findings.

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