ML20235Z435

Forwards Status Rept for Period 870924-1007

ML20235Z435
Person / Time
Site:	Pilgrim
Issue date:	10/14/1987
From:	Blough A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:	Wiggins J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
NUDOCS 8710210141
Download: ML20235Z435 (5)

Text

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2es 14 OCT 1987 Docket No. 50-293 MEMORANDUM FOR: James T. Wiggins, Chief Reactor Projects Branch No. 3 FROM: Allen R. Blough, Chief Reactor Projects Section 3B

SUBJECT:

PILGRIM STATUS REPORT FOR THE PERIOD SEPTEMBER 24-0CTOBER 7, 1987

' Enclosed is the Pilgrim bi-weekly status report from the NRC Resident Office at Pilgrim. The resident inspectors and several region-based specialist inspectors monitored activities at the plant during the report period. i j These status reports are intended to provide NRC management and the public with I an overview of plant activities and NRC inspection activities. Subsequent inspection reports will address many of'these topics in more detail.

Original Signed By:

Allen R. Blough, Chief Reactor Projects Section 3B Enclosure.

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a3g;9 Vk  ; PILGRIM STATUS REPORT FOR THE PERIOD SEPTEMBER 24 - OCTOBER 7,'1987 FW gw e ,

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=1;0 ' Plant" Status

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'CurrentlyJ the plant is in the refueling mode and the refueling activities sm ~ '

are continuing.' ' As 'of ' 9:00 a.m. on October 7, 1987, the licensee had transferred 225 fuel assemblies into the reactor. The reactor core houses

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.a total of 580. fuel. assemblies.

2.0' Facility Operations-Summary

' The plant. hasi been' shutdown'lfor maintenance. and to make program improve-ments since April 12, s 1986. The reactor core was completely defueled on

. February '13,.1987.' ' Following an extensive maintenance and modification of I plant equipment,..the licensee commenced fuel reload on September 29, 1987.

.3.0 Items.of Special-Interest O Reloading of Fuel _into the Reactor On September '27, :1987, 'the licensee decided to delay the scheduled refuelink to conduct additional repairs. During the final review of its pre-re(ueling evaluations, the licensee identified a potential problem with tso . electrical devices (relays) which may not have been operable during a design' basis, earthquake. These electrical devices automatically

@%ll initiate- the Standby _ Gas Treatment System and isolate the secondary-ut containment on a design basis accident condition. The licensee replaced d o" the' electrical devices -.with seismically ' qualified devices and completed l US -

the post-work testing :of Standby Gas Treatment System with acceptable lo 3.' results.

- The Standby Gas Treatment System had been the subject of a deficiency report (unrelated to the above-described electrical relays), pursuant to NRC regulation 10 CFR 21, due to single failure _ susceptibilities. The licensee hadLpreviously completed modifications designed to correct the deficiencies; ' those modifications were reviewed by the NRC inspectors.  !

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.; i On September 29, 1987; i.he licensee completed the pre-refueling evalua-tions:and commenced' refueling about 4:25 p.m. The first fuel assembly was loaded s int'o' the cdra . 'about 5:13 p.m. A total of eight assemblies, two 4 surroundinfeach source range monitor, had been loaded by 10:22 p.m. on {

g Sep tember l 29, 1987. The licensee .then suspended reloading it order to 1' C ' ' y' allow' transfer of new fuel to the spent fuel pool. All ninecy-two ' new f . f el assemblies were transferred to the pool from the storage vault, The i 1 censee resumed reloading the reactor at 7:00 a.m. on October 1,1987.

d. 1e resident and regional inspectors provided continuous coverage of N licensee's refueling sctiv"ities from September 29, through Octobar 2,1987.

.c 3{, As ofi9:00 a.m. .on October 7,1987, the licensee had transferred 225 fuel

)(( /{ assemblies into the reactor. The refueling activities are continuing; a

.t = total of' 580' fuel assemblies will be loaded. The resident and regional

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'Q. g . inspectors are onsite monitoring the refueling activities through both '

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' regular and increased backshift inspections.

Senior Management Meeting (1-

't; OnL September 24, 1987, at the licensee's request, a meeting to brief l senior NRC management on Pilgrim status was held at the NilC headquarters

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offices in Bethesda, Maryland The details of the meeting are documented in meeting minutes issued by. the Office of Nuclear Reactor Regulation on

, Septembar 28, 1987.

g Followup Meeting to the Security Enforcement Conference-n -

Or September 30,193/, a meeting at the licensee's request, was held at 6 I the NRC Region I office in King of' Prussia, Pa. to further discuss the l i c.en see 's proposed corrective actions in response to the violations identified in the security inspection 50-293/87-30. An enforcement j s conference had been held on September 9, 1987. The implementation and r effectiveness of the licensee's corrective actions will be examined (

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during future NRC site inspptions. 1

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NRC Cnymissioner Tours Pilghim

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i[ On Octobeh 5,1987, N36 Commissioner Frederick Ber1 thal toured the Pilgrim licensee led the tour. Commissioner Bernthal- was

'/( 4 facility. 'The I companied by his stiff, Mr. Samuel Collins of Region I, and the resident

, inspectors.

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i 0FFICIAL RECORD COPY PILGRIM BIWEEKLY STATUS 10/7 - 0004.0.0 k 10/23/87 7

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4.0 Emeroency Notification System (ENS) Reports ,

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On October 6, 1987, safety-related 4160 VAC breaker A508 tripped open.

Breaker A508 feeds 480 VAC load center B1 through a 4160/480 VAC trans-former. Load center B1 in turn feeds three safety- related mator control ,

centers and several.significant 120 VAC instrument and logic power busses.

The spurious opening of breaker A508 deenergized the above electrical power distribution equipment resulting in generation of a shutdown cooling system isolation signal. The licensee suspended ongoing refueling activities and initiated an investigation. No definite cause for the spurious breaker trip was identifled. The breaker was reclosed, asso-ciated electrical distribution equipment reenergized and the isolation signal reset. Fuel loading activities were subsequently resumed. The NRC was notified via ENS at 0302 hours0.0035 days <br />0.0839 hours <br />4.993386e-4 weeks <br />1.14911e-4 months <br />. .

. On Septecsber: 28,1987, prior to the start of refueling activities, three 4 unexpected reactor protection system actuations (RPS) occurred in clot.e l succession. The actuations resulted from spurious spiking of several intermediate range monitor (IRM) channels. No rod motion was involved in  ;

any of the three events. Investigation by the licensee identified that welding being conducted in the drywell in the vicinity of the IRM's was the source of the spurious signals. The subject welding activities were l halted and the problem has not recurred. 1 5.0 NRC Staff Sta_tus During the Period  !

The inspection staff at Pilgrim during the "eport period consisted of the following:

Clay Warren ---

Senior Resident Inspector at Shoreham Jeffrey Lyash ---

Resident Inspector Tae Kim ---

Resident Inspector Lawrence Doerflein --- Project Engineer, Region I Roy Fuhrmeister ---

Reactor Engineer, Region I '

Michelle Evans ---

Operations Engineer, Region I 0FFICIAL RECORD COPY PILGRIM BIWEEKLY STATUS 10/7 - 0005.0.0 10/13/87

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