ML20107B334

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Discusses Insp Conducted on 711007-08,which Was Limited to Reviewing Control of Personnel Exposures & Radiation & Contamination Control During Current Extended Outage. No Significant Deficiencies in Program Noted
ML20107B334
Person / Time
Site: Oyster Creek
Issue date: 11/09/1971
From: Meyer R
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To: Robert Carlson
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML18039A986 List: ... further results
References
FOIA-95-258 NUDOCS 9604160228
Download: ML20107B334 (21)


Text

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['i UNITED STATES

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' ATOMIC ENERGY COMMISSION OlVISION OF COMPl.lANCc 2o1 645 3960

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l, MEGION I 97o BROAD STREET

. NEWARK, NEW JERSEY 07to2 NOV 91971 R. T. Carlson, Sr. Reactor Inspector Division of Compliance, Region I

~

CO INSPECTION REPORT No. 50-219/71-03 JERSEY CENTRAL POWER & LIGHT COMPANY OYSTER CREEK 1 - BWR The inspection conducted on October 7 and 8, 1971, which was limited to reviewing control of personnel exposures, and radiation and contamina-tion control during the current extended outage,.showed no significant deficiencies in their program.

Exposure control was maintained on a daily basis with a central control mechanism. Radiation levels in the major work areas were generally low. High radiation areas were well delineated and spoken to in the RWP's covering those areas. All work was controlled by RWP's covering those areas. All work was controlled by RWP's in which work conditions and requirements were well defined.

Contamination control appeared adequate.

The radiation protection staff had been increased by six additional technicians provided by contract from General Electric and Eberline.

The coverage appeared to be adequate to cope with outage problems, however it may have been spread a little thin during the early stages of the' outage.

Two air balance problems noted by the inspector during the inspection apparently had not generated any problems; howevery, they did provide a potential for contamination spreads or high air concentrations outside of radiation zones. Corrective actions to prevent recurrence were initiated.

The licensee currently has no capability to monitor air concentrations on a continuous basis. Licensee has recognized this and is currently investigating their needs. They do sample continuously with the results not being indicative of any problems to date; however the potential for exposure to excessive air concentrations does exist. Licensee agreed to investigate the needs for a bioassay program.

It appears that the current outage has provided experience that will be applied to future outages.

did!^

R. J. Meyer Radiation Specialist 9604160228'960213

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PDR FOIA DEK0K95-258 PDR

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.. g p-U. S. ATOMIC ENERGY COFD11SSION DIVISION OF COMPLIANCE

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I Field Notes for:-

i CO Inspectiop. Report No.

50-219/71-03

'Subj e c t : -

Jersey Central Power & Light Company Oyster Creek 1 License No.

DPR : e v

' Location:

Forked River, N. J.

Priority C

Category _

Type of Licensce: BWR

^

Type of Inspection:

Special, Announced Dates of Inspection:

October 7,1971 Dates of Previous Inspection:

June 22-25 & July 2,1971 Principal Inspector: T. Young, Jr.

Date

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Date

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m U. S. ATOMIC ENERGY' COMMISSION DIVISION OF COMPLIANCE E':CIC ' T Field Notes for:

CO'Inspectiop Report No.

50-219/71-03

Subject:

Jersey Central Power & Light Company Oyster Creek 1 License No._ DPR-16 Location:

Forked River, N. J.

Priority Category C

Type of Licensee: BWR Type of Inspection:

Special, limited, announced Dates of Inspection:

October 7 and 8, 1971 Dates of Previous Inspection:

June 22-25 and-July 2, 1971 Principal Inspector:

R. J. Meyer Date Accompanying Inspectors:

Date Date

. Other Accompanying Personnel:

Date Reviewed By:

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a r

3944 00T 261971 1

1 J. G. Kappler Otief, Reactor Testing & 0perations Br.

4 Division of compliance NQ l'

00 INQUIRY REPCRT NO. 50-219/71-07 JERSEY CENTRAL POWER & LIGHI CWPANY i

OYSTER WEEK - BWR CCSISTRUCTION 12t155 PICKETING TO PROTST THE USE OF GE 1R(PIATIES FOR NAINTENANCE WORK t

The subject inquiry report is forunrded for information.

3 The plant was shut down for renoval of poison curtains, fuel j

replacement / reconstitution, and a turbine warranty inspection at No safety problens were identified with respect to this the time.

)

event.

f No further action is planned by Region I.

I

,,...+

sW4 R. T. Carlson Senior Reactor Inspector i

Enclosure:

Subject I:utuiry Report l'

cc:

E. G. Case, DRS (3) i R. S. Boyd, DRL (2) f R. C. DeYoung DEL (2)

D. J. Skovholt, DEL (3) i H. R. Denton, DRS (2)

A. Giambusso, CO L. Kornblith, CO l

R. H. Engelken, CO Regional Directors, CO DR Central Files 1

i omilit~>A> u f i

I " / fl /p' (

v r.r 7

...,Co,,,,gy,,,

ornce >

Cantrell:smg Carlson sumuc >

oure

.,10/,2p/71

. u.s.oovERMutNTPRIMTINGCFFICEst986-O-364-598 I4'Irm AEC.318 (Rev. 9-63)_

r,

7 4

i k

CO Inquiry Report No. 50-219/71-07 3

i I., m.

Subject:

Jerser e-- ^ ral ;-- = 6 IA At M any

..;, e

'I#

~

License No.: DPR-16 Facility:_ Oyster Creek (BWR)

Title:

Construction Unions Picketing to Protest the 1

4 Use of GE Employees for Maint-eace Work Prepared bys_

{,

P. S. Caustrell, Reactor Inspector Date 4.- e z

A.

Date and F - r ABC was Informed:

In telephone conWrsation with Plant Superintendent; T. McCluskey a

l at 9:00 mm, October 26, 1971.

j B.

Description of Particular Event or Ciretanstance:

1 At 6:00 am October 23, 1971,

.Buildias. Trades Assoaistien put*out piehete et the entrances tothe M M

the byster Creek Nuclear Generating Station protesting the use of General Electric Company employees to perform maintenance and repair work. The normal day shift crew reported for work at i

4:00 am as scheduled, but a special crew for handling fuel was i

turned back at 8:00 mm as well as CE employees performing warranty work on the main turbine and the core spray system check valves. Discussions were held between JCP&L and the Building Trades representatives.

Ten maintenance, supervisory and technical personnel were allowed in the plant at 2:00 pm.

'Ibe 4 - 12 shift was permitted to enter and the pickets were with-i drawn at 6:00 pm. The net effect was approximately 1 day lost time for the outa8e. Mr. McCluskey stated that the plant always had at least the required number of licensed personnel to run ~

i the plant and no safety problems were encountered.

C.

Action by Licensee:

4 No further action is planned at this time. According to Mr.

McCluskey, JCP&L Co. does not normally use construction trades people in any of their plants for maintenance and repair work.

I' n) o

.2 m n w-v~r;;im w

.4 4

3944 OCT 71971 4

%,w.

g J. G. Keppler, Qttef, Reactor Testing is operations Br.

)

Division of compliance HQ 1

00 INQUIRT REFWT NO. 50-119/71-06 JEtsar cEnr:AL romm & LIGRT CO. (OTSTER CREEK - BWR) 00 INSFECTM REVIW OF RESULT 8 0F FDEL SIPPING -

1 l,

LICENSEE REFUELING PLANS The attached inquiry report is forwarded for information in advance

.,a 3 of a detailed inspection report.

.. v Preliminary results of our inspection indicate that the licensee's refueling activities are proceeding according to plans with no t

major difficulties having been encountered to date.

We intend to continue following closely the current outage and will keep'you informed as is appropriate.

4

.g.

+

.i.

R. T. Carlson Senior Reactor Inspector Enclosures l

Inquiry Rpt 50-219/71-06 l

ect E. G. Case, DRS (3)

R. 8. Boyd, DRL (2)

R. C. Deroung DEL (2)

D. J. Skovholt DRL (3)

H. R. Denton, DR8 (2) i A. Giambusso, 00 L. Kornblith, CO R. Engelken,~ CO Regional Directors, CO DR Central Files

(

. 9 x A LJ_n > 1 iase(

1

- a y < r ---

e omer >

SURNAME >

...O.

I03.

~O 80g 10/7/71 o4rc >

IWin A EX3-3iH (H.v. 9-.63)

U,s. Govtiteturnt reiniino orrict itse-o-ss4-ses

00 Inquiry Report No. 50-119/71-06 p

Subject:

Jerser central Power 6 'Mt Osmoamy l,:

License No.: DPR-16 Facility: Oyster Creek 1 (BWR)

Title:

00 Inspector Review of Results of Fuel giopina -

Licenses ma halina Plans Prepared by:

F. g. Centre 11. Reactor Inspecter Date A.

Date and Manner AEC was i=8 H :

Getober 7, 1971 during a telephone conversation with Yolbert Young, Jr., Reactor Inspector, do is currently at the site reviewing refueling activities.

B.

Description of Particular Event or Circumstances the planned 2f'

. Mr, Ygung reported that the,1isenese Aes completed d 11es"on the,;.,

g

_m

. fuel ' sipping ~ of the resetor core. ' All bu(12 asse

^

periphery were sipped. He results indicate 44 of the 548 assemblies sipped contain one or more leaking fuel pins. All of the identified lenkers were located in the high flux region (central) of the core. The licensee believes that the probability' of the rammininr 12 assemblies being Isakers is very low.

C.

Action by Licenses:

According to Mr. Young, the licensee plans to replace 24 of the lesking assemblies with assemblies from the periphery of the i

core, with the latter assemblies being replaced with new fuel l

assemblies. Os rammining 20 leaking assenblies will be recon-i siituted, replacing identified leaking fuel pins with non-leaking l

pins from the removed assemblies as neceesary.

t' h

jg '

r.

8 I

i

N 3944 SEP 101971 x

hi4 a

J. G. Kappler, Chief, Jeetor Testing and Operations Branah, Division of Cu ylianee, NQ

-EVALUATION HINORANDtB(

CO INQUIRY REPORT No. 50-219/71-05 JERSEY CENTRAL POWER 4: LISET 00. (Of8TER CREEK - BUR)

Is0MTION CONDENBER REMY FAILDRE The attaehed Inquiry Report relating to the failure of ties delay relays asooeisted with the isolation condenser is forverded for

,W information. The action taken by the licenses appears to be adequate.

It is raahad that a survey of other BWR licensees be conducted to determine their esperience with this type relay. From the enount of troubist JC has superienced, it would appear that this relay is not reliable for this type service. We plant. to review this subject with Nine Mile Point and Hillstone. We will keep you informed as t

appropriate.

3 w

mqlM-

. ~..

m.

.x i

R. T. Carlson p-Senior Reactor Inspector l

f

Enclosure:

j j

CO Inquiry Rpt. No. 50-219/71-05 i

cc E. G. Case, DR8 (3)

I

1. S. Boyd, DEL (2) l R. C. DeYoung DEL (2)

D. J Skovholt DRL (3) 4 H. R. Denton, DRS (2) l A. Gianbusso, CO L. Kornblith, CO i

l R. H. Engelken, CO Regional Directors, CO l

DR Central Files 4

4

=(y3 eb o n A 11 s 3 2 > uo A i

omcc>

...CQ.........

--*Gv

$URNAME>

..h 0,0

.h,*. Sm$

Ca Son,,

9/10/71

~"

i,..m.,, -,,.., _ n,...

nwm ac-we m. m

0

~

/

l 00 Inquiry Report No. 50-219/71-05 94 ject:

Ja--- Central Power & tiskt Co.

l Ni f

License No.I M R-14 Facility: orstar creek dium) i

Title:

Iso 1=ed-r'-:-'

_r Balar Failure l

Prepared bys Date F. s. Centre 11, Jr., Reactor inspector A.

Date

' =

- N Was inermead:

Mr. Ten McCluskar, Station Superintendent, reported the matter 1.

Additional infoens-by phone to Region I on September 8, 1971.

tion was obem4==d in phone conversatio.as with Nessrs. McCluskey and Joe Carroll, Operations supervisor, on September 9, 1971.

B.

Descristiaa of Eventt On septand>er 3, 1971 W ils conducting a surveillance test to 2.

insure isolation of the two redundant isolation aandan=ers the two reigys on 5 isolation

..upon detestaan of a line break, ion in the event of a ties 6 46 n.

condenser, Aish initiate isolat (Previous failures of isolation break, would not operate.

candammer relays were reported to DEL in letters from I. R.

Finfrock dated May 17 and July 21,1971.)

The rel gs that activate the isolation condenser were still 3.

In the event of a line break, the condensers could operable.

have been isotted manually.

C.

Action by Licenses Due to the physical location of the relays in the control 4.

board, the failed relays were not removed; however, the wiring was disconnected from the old relay (CE CR 120) and a replace-ment thee delay relay (Agastat 7022PD)'was installed at an accessible location. h e Agastat relay performs the sane func-All eight of the GE type relays associated with the tion.

isolation condensers have now been replaced with the Agastat relays.

One of the relays that failed previously was exanined and 5.

the cause of failure was detennined to be differential expan-sion resulting from overheating. Ihe heat source is a registor he differential expansion physically presrented in the relay.

operation of the relay.

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Ber. Carroll stated that JC is reviewing their instrumentation j $,$y to ses if the os reig is used in other services et the plant.

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Mr. McCluskey stated that JC would submit a written report of the most recent feiture to DEL in accordance with the requires ments of the license.

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