ML17199F997

Insp Rept 50-237/87-05 on 861201-870108.Violation Noted:On 861128 & 29,plant Operated for Over 24 H W/Drywell to Suppression Chamber Differential Pressure Less than 1.00 Psid

ML17199F997
Person / Time
Site:	Dresden
Issue date:	01/16/1987
From:	Wright G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML17199F998	List: IR 05000237/1987005 ML17199F997
References
50-237-87-05, 50-237-87-5, NUDOCS 8701280466
Download: ML17199F997 (3)

See also: IR 05000237/1987005

Text

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U.S. NUCLEAR REGULATORY COMP'.JSSJON

REGJON III

Report No. SO-Z37/S7005(DRP)

Docket No. S0-237

License No. DPR-19

Ltcensee:

Common~ea1th Edison Company

P. 0. Box 767

Chic1go, IL 60690

F1c11ity Name:

Dresden Nuclear Power Station, Unit Z

Inspection At:

Dresden Site, Morris, Illinois

Inspection Conducted:

December l, 1986 through January 8, 1987

Inspectors:

L. G. McGregor

P. D. Kaufman

N. V. Gilles

P,,{,_/?J ~- ~~ -11_

Approved By:,/'~~ey C. Wri;.t;: Chief

I

Reactor Projects Section ZC

Date

Inspection Summary

Jns ection on December l

1986 throu h Januar 8 1987

Re ort

No. S0-237/B7005 DRP

Areas Inspected: Special inspection of the circumstances surrounding the

event involving oper1tion of Dresden Unit Z 1n viol*t1on of its license on

November 29, 1986.

Results: One 1pparent violation of 10 CFR S0.36 with t~o exa~ples was

identified when Dresden Unit 2 was operited for greater than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> with

drywE 11 to_..* suppress ion charr.!:>er different ii 1 pressure less than l. DO psid and

for great,~r'than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> following comrr.encement of deinerting 1ctivities.

I

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DflAJLS

1.

Ptrsons [ont1ctrd

(om~onwe11th Edison Company

• [. (tn1~enburg, St1t1on M1n1ger

• J. Wujt1QI, Production Super1ntfndent

• R. Flessner, Services Superintendent

• M. Jeisy, QA Supervisor

• J. Brunner, Assist1nt Superintendent, lechn1c1l Services

• J. Almer, Unit 2 Oper1t1ng Engineer

• J. lotowsl1, Unit 3 Oper1ting Engineer

• o. Ad*"'** Compli1nce Administntor

J. Williams, Tech Stiff

R. F1cchin1 1 Shift Engineer

T. P1lanyl, St1tion Control Room Engineer

J. Gilligan, Shift Engineer

1. Mohr, Station Control Room Engineer

The inspectors 1lso talked with and interviewed sever11 other licensee

employees, including ~embers of the technical and engineering staffs,

re1ctor and auxiliary operators, shift engineers and foremen.

• Denotes those 1ttending one or *ore exit interviews conducted on

January 8, 1986, and informally at various times throughout the

inspection period.

2.

Event Description

On November 28, 1986, the licensee was nearing the planned refueling

shutdown of.Unit 2 and elected to commence de1nerting the drywell

2~ hours before the plant was to be shutdown.

This action 1s permiited

under Technic1l Specific1tion Limiting Conditions for Oper1tion

(LCO) 3.7.A.S.b. and 3.7.A.7.a(l). At 1220 hours0.0141 days <br />0.339 hours <br />0.00202 weeks <br />4.6421e-4 months <br /> on November 28, 1986,

with the re1ctor at 72 percent power, drywell pressure at 1.20 psig, an~

torus pressure 1t 0.01 psig, the two inch equalizing line between the

dryvell and the torus was opened.

Th1s 1ction commenced the deinert1ng

of*_the containment 1tmosphere in accordance wiU1 Dresden Operating

Procedure (DOP) 1600-8, Revision 8, "Deinert ing of Primary Conu1nment

Thtough the Reactor Building Ventilation System.* At 1448 hours0.0168 days <br />0.402 hours <br />0.00239 weeks <br />5.50964e-4 months <br /> that

same day, the licensee opened the containment vent and purge valves per

DOP 1600-8. Prior to opening these valves, containment oxygen

concentration *easured approx1mate1y 3.4 percent. Containment oxygen

concentration exceeded 4 percent within several ~inutes of opening the

vent and purge valves.

At 2320 hours0.0269 days <br />0.644 hours <br />0.00384 weeks <br />8.8276e-4 months <br />, the shift operators began to

insert control rods to reduce reactor po~er.

0~ lovember 29, 1986, It 0135, 0237, Ind 0400 hours0.00463 days <br />0.111 hours <br />6.613757e-4 weeks <br />1.522e-4 months <br />, the licensee made

unsuccessful attempts to fast start the High Pressure Cool1nt Injection

(HPtl) pump to satisfy 1 commitment made to the Institute for Nuclear

P°""'r Operations (JNPO) by the licensee. At 0916 hours0.0106 days <br />0.254 hours <br />0.00151 weeks <br />3.48538e-4 months <br />, the main generator

lDid was reduced to 1 value sufficient to disconnect the Unit 2 generator

fror the grid.

~c.ir. stfal7 by-pa~~ vahe~ \\.'ere u5ed to rr.c.iritcir, the reactor

2

• thrnnal powrr 1t or 111ghtly 9rt1ttr thin JS prrctnt, wh11t thr rt1ctor

• aodr 1w1tch rtma1ntd tn thr run pos1tton. That oprr1t1on11 conf19ur1tton

1upplttd 1ufftcttnt stt1m to complttt tht NPCJ ttsttng. At approat~atrly

lSOO hours, tht oncom1ng Sh1ft [ng1nttr tnttrtd tht control room end

1dv11td p11nt ~anagtment of the ntrd to shutdo~n the rractor to rt11tve

the plant. frorr, thou LCOs which rtqu1red untt shutdown by lZZO hours on

November 29, 1986.

Upon rev1ew 1nd d11cusston of thr sttu1tton by

the Oper1t1ng Staff and ltcensee ~1n1gement, tht ltcenstt dec1ded to

complete the HPCJ ttsttng before reactor 1hutdo~. At 1600 hours0.0185 days <br />0.444 hours <br />0.00265 weeks <br />6.088e-4 months <br />. the

ltcensee nottfttd the NRC Duty Offtcer vta the Emrrgency Nottftc1tton

Syste~ (ENS) th1t 1n Unusual Event had been decl1red at 1545 under

Gener1t1ng St1tton Emergency Plan Emergency Actton Level (EAL) 3.1.

EAL 3.1, ~loss of Plant Systems,M cl1sstfies degr1d1tton of equtpment

addressed tn the Techntc1l Spectftc1tions requiring plant shutdown as an

Unusual Event. The f1n11 HPCJ test started 1t l~CS hours and was

tenntn1ted as 1 successful fast start (Spectal Procedure 86-11*152) 1t

1611 hours0.0186 days <br />0.448 hours <br />0.00266 weeks <br />6.129855e-4 months <br />. At 1703 hours0.0197 days <br />0.473 hours <br />0.00282 weeks <br />6.479915e-4 months <br /> the reactor mode sw1tch w1s placed tnto

shutdown to 1n1t11te 1 manual reactor scram end 1t 1710 hours0.0198 days <br />0.475 hours <br />0.00283 weeks <br />6.50655e-4 months <br /> the

Unusual Event was terminated.

One violation of JO CFR 50.36 was 1dent1fied for operation of Dresden

Unit 2 tn violation of Technical Spec1ficatfons 3.7.A.5.b and 3.7.A.7.a(l).

Those specific1t1ons requ1red the un1t to be shutdown by 1220 hours0.0141 days <br />0.339 hours <br />0.00202 weeks <br />4.6421e-4 months <br /> on

November 29, 1986.

The reactor w1s not shutdown as requ1red unttl

1703 hours0.0197 days <br />0.473 hours <br />0.00282 weeks <br />6.479915e-4 months <br /> on November 29, 1986.

3.

Extt Jntervtew

The tnspectors 11et with ltcensee representatives (denoted tn P1ragr1ph 1)

tnfo~a 11y throughout the tnspect ton pertod and at the concl us ton of the

tnspection on January 8, 1987, and summarized the scope and findings of

the tnspection acttvtttes. The inspectors stated that the NRC plans to

conduct 1 eeet1ng with the licensee to discuss the detatls of the

vtolatton tdent1f1ed durtng this tnspectton.

The tnspector discussed the ltkely tnfonnatton1l content of the

inspection report with regard to documents or processes revtewed by

the tnspector during the 1nspect1on.

The 11censee did not identify

any such documents/processes as proprietary.

The licensee acknowledged

the-.findings of the inspection.

3