IR 05000336/1993081

Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-336/93-81

ML20059K824
Person / Time
Site:	Millstone
Issue date:	11/09/1993
From:	Durr J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:	Opeka J NORTHEAST NUCLEAR ENERGY CO.
References
NUDOCS 9311160209
Download: ML20059K824 (2)

Text

{{#Wiki_filter:, , ' 'b 4: !

NOV 9 1993 y ! -i, Docket No. 50-336 Mr. John F. Opcka Executive Vice President - Nuclear l Northeast Nuclear Energy Company , P. O. Box 270 Hartford, Connecticut 06141-0270

Dear Mr. Opeka:

, SUBJECT: INSPECTION REPORT NO. 50-336/93-81 This letter refers to your August 24,1993, correspondence and the amended letter, dated September 22,1993, in response to our June 25,1993, letter.

Thank you for informing us of the scheduled completion dates of the corrective and preventive actions for the 13 items identified in Inspection Report No. 50-336/93-81. These ' actions will be examined during a future inspection ~of your licensed program.

Your cooperation with us is appreciated.

Sincerely,

cn ua sn.,e y Jacque P. Durr, Chief

Engineering Branch . Division of Reactor Safety i !

!

' Mja16o209932109 ADOCK 05000336 n/ G PDR , ()[ i / ' ]I !

- ' ' - t20V 9 1993

Northeast Nuclear

Energy Company cc: W. D. Romberg, Vice President - Nuclear, Operations Services S. E. Scace, Vice President, Millstone Station

J. P. Stetz, Vice President, Haddam Neck Plant - G. H. Bouchard, Nuclear Unit Director i R. M. Kacich, Director, Nuclear Licensing J. Solymossy, Director, Nuclear Quality and Assessment Services Gerald Garfield, Esquire Nicholas Reynolds, Esquire Public Document Room (PDR) > Local Public Document Room (LPDR)

Nuclear Safety Information Center (NSIC) NRC Resident Inspector State of Connecticut SLO bec w/ encl: , Region I Docket Room (with concurrences) , V. McCree, OEDO . G. Vissing, PM, NRR J. Stolz, NRR/PD I-4 .. l i s . . i [W) '

.

' l.4c-RI:DRS RI:DRS RI:DRS

Cheung Ru [ Durr ' is/ A/93 6/ /93 16/9 /93 t OFFICIAL RECORD COPY ' A:336-9381. REP ,

'

f

., ,_ . NORTHEAST UTILITIES cenere on ce semen stren Bernn Conn *ticut ' . .., c m w y ~. s.-~ . P.O. BOX 270 .. .,v, mwm m *. n--

.m..,.w.w**

H ARTF ORD, CONNECTICUT 06141-0270 L L y [[[g'j'[*,[ (203) 665-5000 August 24, 1993 Docket No. 50-336 B14589 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 Gentlemen: Millstone Nuclear Power Station, Unit No. 2 Inspection Report No. 50-336/93-81 Schedule for Resolution of Unresolved items In a letter dated June 25, 1993,2 the NRC Staff transmitted Inspection Report No.

50-336/93-81 to Northeast Nuclear Energy i Company (NNECO).

The inspection report provided the results of an electrical distribution system functional inspection conducted , during the period between March 15 and April 2, 1993.

Based upon-the results of the inspection, the NRC Staff identified

unresolved items.

Attachment 1 to this letter provides NNECO's schedule for resolution of the 13 unresolved items, on behalf of Millstone Unit No.

2, in accordance with the instructions contained within the inspection report.

We trust that you will find this information satisfactory.

We remain available to answer any questions you may have.

Very truly yours,

l NORTHEAST NUCLEAR ENERGY COMPANY . . - R, b (,h eLu J. l v Executive Vice President cc: T.

T.

Martin, Region I Administrator G.

S. Vissing, NRC Project Manager, Millstone Unit No. 2 P.

D. Swetland, Senior Resident Inspector, Millstone Unit + Nos.

1, 2, and 3 '

M.

W.

Hodges letter to J.

F.

Opeka, " Notice of violation, NRC Inspection Report No.

50-336/93-81," dated June 25. 1993.

m, I i _2 rm - r s.

\\ d h i -

.. .,, - ... ... ..... -.. ....... - . -,.,,,. ,. u.,... . -. ',- .. .a.. . ., , t . -. ..,. . , ' ,

.

- Docket No.-50-336 ' B14589' . ' . g ? i .j . -... . _.

q t

, ! '; Attachment 1 i Millstone Nuclear Power Station, Unit 11o. 2 ! t Inspection i.eport 50-336/93-81- ! i i Schedule for Resolution of Unresolved Items j . ;- ? , v ! .! ! ! t i i l .'. i l J ! . i . 'i i

., r

>

l

i

. .i

I .; ' ' ? ., August',1993 ~ t ! r ' '

I

3,

-.. ,.. _.. _.. _,. _,. _., .

'

.. . . ' .

Millstone Nuclear Power Station Unit No. 2 ' .- Inspection Report 50-336/93-81 Schedule f or ResoPation of Unresolved Items t - l DESCRIPTION OF UNRESOLVED ITEM UNRESOLVED ITEM # COMPLETION DATE

1.

Emergency Diesel Generator 93-81-03 6/30/94' l' (EDG) loading calculations to be finalized.

2.

EDG transient analyres to be 93-81-04 6/30/96 p 4b4

verMied by test data.

1. MS

'/ , j 3.

Ve.i-ecovery of 4160 V 93-81-05 12/31/96 g~ grth [ emer9 buses after loss of - f { '7 g f. 7 - 5p C) k j coolg (LOCA) load is g applied.

' 'r . -+ 4.

Fast transfer dead bus time to 93-81-01 12/31/94 } be verified by-test data.

I ! 5.

Phase angle of 300 in fast 93-81-02 12/31/94 - transfer permissive signal to be justified.

l 6.

AC short circuit calculation 93-81-06 6/30/96

used non-conservative i conductor temperature.

7.

FSAR commitment of 7-day EDG 93-81-08 12/31/93 fuel supply and EDG rating.

8.

Maximum high-voltage 93-81-11 10/31/93 switchgear room temperature-differs from FSAR commitment.

9.

Maximum intake structure 93-81-10 COMPLETE ! temperature differs from FSAR

commitment.

10.

Adequacy of housekeeping 93-81-12 10/4/94 procedure for dealing with ' loose equipment temporarily stored in safety related areas.

11.

EDG overcurrent protection not 93-81-07 6/30/96 supplied with two or more independent measurement and no ! coincident logic for trip . actuation.

! 12.

Seismic and tornado on EDG 93-81-09 IPEEE scheduled fuel supply tank to be to be submitted incorporated into IPEEE in the second program.

quarter of . 1995"' ! L t ! i (1) J. letter to U.S.

Nuclear Regulatory Ccmmission, "Haddam Neck Plant, Millstone Nuclear Power Station, Unit Nos.

1, 2, and 3, Response to Request for Additional Information,* dated September 18,-1992.

.

,

. . ,

o Millstone Nuclear Power Station Unit No. 2 .. Inspection Report 50-336/93-81 Schedule for Resolution of Unresolved Items DESCRIPTION OF UNRESOLVED ITEM UNRESOLVED ITEM # COMPLETION DATE 13.

Insufficient pickup voltage 93-81-15 12/31/93'2' for pump starter coils.

, (2) This condition was reported in Licensee Event Report 50-336/93-008 submitted to the NRC Staff en June 1, 1993.

The LER identified that administrative centrols had been established to ensure the minimum Technical Specification requirements for the charging system are satisfied, and that the long term solutien would be a modification to eliminate the cabling voltage drop to provide sufficient voltage at the starter relay coil.

This is the schedule for completion of this modification.

'

. , '. .. N t#TILITIES c,.ner.i On.c... s.io.n sir..t. Boriin. Conn cticui

.- I P.O. BOX 270 ' '

S c' c a

• " **** *" " "

HARTFORD. CONNECTICUT 06141-0270 k k J Z%7n,7,*C (203) 665-5000 September 22, 1993 - Docket No. 50-336 B14621 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 Gentlemen: Millstone Nuclear Power Station, Unit No. 2 Inspection Report No. 50-336/93-81 Revised Schedule for Resolution of Unresolved Items , In a letter dated June 25, 1993,"' the NRC Staff transmitted Inspection Report No. 50-336/93-81 to Northeast Nuclear Energy Company (NNECO).

'The inspection report provided the results of an electrical distribution system functional inspection conducted during the period between March 15, and April 2, 1993.

Based upon the results of the inspection, the NRC Staff identified 13 unresolved items.

By letter dated August 24, 1993,i23 NNECO provided a schedule for resolution of the 13 unresolved items for Millstone . Unit No. 2, in accordance with the instructions contained within -the inspection report. Upon review of NNEC0's response, the NRC Staff asket if it would be possible to complete resolution of four of the items earlier than the schedule provided for unresolved items 93-81.04, 93-81-05, 93-81-06, 93-81-07.

NNECO has reevaluated the schedule for the four unresolved items and has determined that the items can be resolved sooner than initially planned.

NNECO discussed the revised schedule with the EDSFI team leader, Mr. Leonard Cheung, on September 13, 1993.

Mr. Cheung requested that NNEC0 submit a revised schedule for the four unresolved items and include a discussion of the reasons for the dates provided for unresolved items 93-81-04 and 93-81-05.

Attachment I to this letter provides the requested information.

(1) M. W. Hodges letter to J. F Opeka, " Notice of Violation, NRC Inspection Report No. 50-336/93-81," dated June 25, 1993.

(2) J. letter to U.S.

Nuclear Regulatory Commission, " Millstone Nuclear Power Station, Unit No. 2, inspection Report No. 50-336/93-81, Schedule for Resolution of Unresolved Items," dated August 24, 1993.

' r 0D l f* p(' v iv

- 47 os3m nev tas

. . .. . , b b U.S. Nuclear Regulatory Commission B14621/Page 2 September 22, 1993 We trust that you will find this information satisfactory.

We remain available to answer any questions you may have.

Very truly yours, __ ' NORTHEAST NUCLEAR ENERGY COMPANY FOR: J. Executive Vice President ' BY:

W. D. Rombers' Vice President cc: T. T. Martin, Region I Administrator G. S. Vissing, NRC Project Manager, Millstone Unit No. 2 P. D. Swetland, Senior Resident Inspector, Millstone Unit Nos.1, 2, and 3 .

h

, ; '

,. ,- Docket No. 50-336 B14621 _ Attachment 1 Millstone Nuclear Power Station, Unit No. 2 Inspection Report No. 50-336/93-81 Revised Schedule for Resolution of Unresolved Items September 1993 -

I /, .* , . .

. U.S. Nuclear Regulatory Commission B14621/ Attachment 1/Page 1 September 22, 1993 , Millstone Nuclear Power Station Unit No. 2 Inspection Report 50-336/93-81 -- Revised Schedule for Resolution of Unresolved Items DESCRIPTION OF UNRESOLVED ITEM UNRESOLVED ITEM NO.

COMPLETION DATE EDG transient analyses to be 93-81-04 12/31/94 verified by test data.

Voltage recovery of 4160 V emergency buses after loss of 93-81-05 12/31/94 coolant (LOCA) load is applied.

AC short circuit calculation used non-conservative conductor 93-81-06 6/30/95 temperature.

EDG overcurrent protection not supplied with two or more independent measurements and no 93-81-07 6/30/95 coincident logic for trip actuation.

Unresolved item 93-81-04 requires testing which will be performed in the next refueling outage (Cycle 12), presently scheduled to take place during the summer of 1994.

Once the tests have been completed, test reports will be written, reviewed, and approved.

The results will be evaleated and findings, if any, dispositioned.

NNECO estimates that these activities ran be completed by December 31, 1994.

However, as these efforts are tied to outage activities, any significant changes to the outage schedule 'nay have a corresponding affect on the scheduled completion date.

Resolution of item 93-81-05 requires computer-generated modeling-calculations.

Tests are planned during the next refueling outage to verify assumptions /results of the computer modeling.

The results will be evaluated and findings, if any, dispositioned.

NNECO estimates that these activities can be complete by December 31, 1994.

However, as these efforts are tied to outage activities, any significant changes to the outage schedule may have a corresponding affect on the scheduled completion date. }}