05000336/LER-1995-001, :on 950118,crane Operated Over Spent Fuel Pool While Enclosure Bldg Ventilation Sys Inoperable.Caused by Inadequate or Insufficient Procedures.Ts 3.9.7,3.9.14 & 3.19.15 Will Be Reviewed for Clarifications

:on 950118,crane Operated Over Spent Fuel Pool While Enclosure Bldg Ventilation Sys Inoperable.Caused by Inadequate or Insufficient Procedures.Ts 3.9.7,3.9.14 & 3.19.15 Will Be Reviewed for Clarifications

ML20080H602
Person / Time
Site:	Millstone
Issue date:	02/15/1995
From:	Lutzi P, Miller D NORTHEAST NUCLEAR ENERGY CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-95-001, LER-95-1, MP-95-061, MP-95-61, NUDOCS 9502220396
Download: ML20080H602 (4)

LER-1995-001, on 950118,crane Operated Over Spent Fuel Pool While Enclosure Bldg Ventilation Sys Inoperable.Caused by Inadequate or Insufficient Procedures.Ts 3.9.7,3.9.14 & 3.19.15 Will Be Reviewed for Clarifications

Event date:
Report date:
Reporting criterion:	10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
3361995001R00 - NRC Website

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' N:rtherst Rope Ferry Rd. (Route 156), Waterford, Cr 06385 Nuclear Energy Mmstone Nuclear Power Station Northeast Nuclear Energy Company P.O. Box 128 I

Waterford, CT 06385-0128 (203) 444 -4300 Fax (203)444-4277 The Northeast Utilities System Donald B. Miller Jr.,

Senior Vice President - Millstone Re: 10CFR50.73(a)(2)(i)

February 15, 1995 MP-95-061 lj.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555

Reference:

Facility Operating Ucense No. DPR-65 Docket No. 50-336 Licensee Event Report 95-001-00 This letter forwards Licensee Event Report 95-001 -00 required to be submitted within thirty (30) days pursuant to 10CFR50.73(a)(2)(i).

Very truly yours, NORTHEAST NUCLEAR E MPANY

1. 1 Donald B. Miller, Jr.

Senior Vice President - Millstone Station DBM/MH:dir Attachment: LER 95-001 -00 co:

T. T. Martin, Region 1 Administrator P. D. Swetland, Senior Resident inspector, Millstone Unit Nos.1, 2, and 3 i

G. S. Vissing, NRC Project Manager, Millstone Unit No. 2 l

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9502220396 95o215 vl1, i DR ADOCK 0500 6

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NRC Form 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED RY OMB NO. 3150-0104 (5-92)

EXPIRES: 5/31/95 ESTIMATED BURDEN PER RESPGlt%E TO COMPLY WITH THiS INFOMATION COLLECTCN KIOCIST: 509 HRS FC3 WARD COMMENTS KIGARDING LICENSEE EVENT REPORT (LER)

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WASHINGTON. DC 20555-0001 AND TO THE PAPERWORK REDUCTIDN (Sea revede for rhulred number of chgits/ characters for each blacit)

ASH NOT DC FACILITY NAME (1)

DOCKET NUMBER (2)

PAGE (3)

Millstone Nuclear Power Station Unit 2 05000336 1 OF 3 rm.E e)

Crane Operation Over Spent Fuel Pool with Ventilation inoperable EVENT DATE (5)

LER NUMBER (6)

REPORT DATE (7)

OTHER FACILITIES INVOLVED (8)

SEyQ l R S MONTH DAY YEAR FACIUTY NAME DOCKET NUMBEh MONTH DAY YEAR YEAR 05000 j

FACluTY NAME DOCKET NUMBLR 02 15 95 01 18 95 95 001 -

00 05000 OPEnATiwo THIS REPORT IS BEINO SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR 6: (Check one or more) (11)

MOcE m N/A 20 m) me>m nism

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POWER 20 405(nH1)C) 50 36(c)(1) 5013(a)(2)M 737 tic) 20.405(a)(1)(ii) 50 36fe)(2) 50 73(a)(2)MQ OTHER 20,40S(a)(1)(iii)

V 5013(a)(2)t) 50J3(a)(2)(viii)(A)

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20 405(a)(1)(iv) 5013(a)(2)(li) 50 73(a)(2) Mil)(B)

Form mA) 20 4064a)(11tv) 50 73ta)(2)oll) 50 73(a)(2)(x)

LICENSEE CONTACT FOR THIS LER (12)

NAME TrlFPHONE NUMRf A finclutte Area Corfe)

Philip J Lutzi, Nuclear Licensing (203) 440-2072 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRISED IN THIS REPORT (13)

REPORTABLE HEPORTABLE

CAUSE

SYSTEM COMPONENT MANUFACTURER TO NPRDS

CAUSE

SYSTEM COMPONENT MANUFACTURER TO NPRDS i

SUPPLEMENTAL REPORT EXPECTED (14)

EXPEC1ED U^#

SUBMISSION YEs i

no X

DATE (15)

(if yes, compeia FXPECTED SUBMISSION DATE)

ABSTRACT (uma to 1400 spaces,la apprommaieiy 15 sncie-spaced typentsten unes)(1s)

On January 18,1995 at approximately 1000 hours0.0116 days <br />0.278 hours <br />0.00165 weeks <br />3.805e-4 months <br /> with the plant shutdown and defueled, millwrights involved in routine maintenance of refueling equipment conducted operations of a small crane over the spent fuel pool with a load on the crane while the enclosure building ventilation system was inoperative. Technical Specification 3.9.15 does not allow operation of craries with a load over the spent fuel pool when the ventilation system for the area is not operable and capable of automatic initiation in the auxiliary mode. The crane utilized was a small monorail hoist rated at 5 ton and the load was approximately 80 pounds. The cause of the event is attributed to inadequate

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or incomplete procedures. The corrective action will be to review the Technical Specifications (3.9.7,3.9.14 and 3.19.15) for clarifications and changes necessary to provide proper guidance. The signif;cance of the event is low in that there was no practical way to cause an event that would have resulted in the release of radioactivity, i

NRC Form 356 (5-92)

NRC Form 306A U.s. NUCLEAR REGULATORY COMMisslON APPROVED BY OMB NO. 3150-0104 O~8D EXPIRES: 5/31/95 LICENSEE EVENT REPORT (LER)

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FACIUTY NAME (1)

DOCKET NUMBER (2)

LfR NUMBER (6)

PAGE (3) 0 NUMFW YEAR NUM Millstone Nuclear Power Station Unit 2 05000336 95 001 -

00 02 OF 03 TEXT tu ma e space is reewed, une adenones copies Of NRC Farm $66A) (17) 1.

Descriotion of Event On January 18,1995, at approximately 1000 hours0.0116 days <br />0.278 hours <br />0.00165 weeks <br />3.805e-4 months <br /> with the plant shutdown and defueled, millwrights involved in routine maintenance of refueling equipment conducted operations of a small crane over the spent fuel pool with a load on it when the enclosure building ventilation system was inoperative.

Technical Specification 3.C.15, Storage Pool Area Ventilation System - Fuel Storage requires that at least one enclosure building filtration syctem (EBFS) shall be operable and capable of automatically initiating operation in the auxiliary exhaust (AFM) mode whenever irradiated fuel is in the spent fuel pool. if the system is not operable, no crane op % tion with loads over the pool is allowed.

On the above date a work crew was briefed and sent to replace a light bulb 'n a spent fuel pool underwater lamo which weighed approximately 80 pounds. The job leader chose to utilize the 5 ton rated monorail rnounted crane to assist in lifting the lamp from the spent fuel pool, which by the Technical Specification is not allowed when the EBFS is inoperable. At the completion of the job and upcn further discussion with reactor engineering personnel, it was decided that this event was in violation of the Technical Specification and should be reported.

There were no automatic or manually initiated safety systems as a result of this avent.

1 II.

Cause of Event

The root cause of the event is inadequate and/or incomplete procedures which was compounded by the fact the three Technical Specifications that are applicable (3.9.7,3.9.14 and 3.9.15) are not consistent in I

their treatment of loads over the spent fuel pool.

Ill.

Analysis of Event

This report is being submitted pursuant to the requirements of 10CFR50.73(a)(2)(i)(B), "any operation or condition prohibited by the plant Technical Specifications."

There were no safety consequences of this event, nor could an event with any safety consequences have occurred if the load had fallen from the crane into the spent fuel pool.

Although the LCO and basis for 3.9.15 gives no guidance as to what constitutes a load it does address the fact that the LCO is meant to ensure that the radioactivity released from an irradiated fuel assembly will be filtered prior to discharge to the atmosphere. From this statement, it is obvious that the basis for this specification is the fuel handling accident.

FSAR Section 14.7.4.2 of the Radiological Consequences of Fuel Handling Accidents section discusses the types of fuel handling accidents that are con'idered for Millstone Unit 2. The FSAR analysis acknowledges that a dropped fuel assembly can only hit one other fuel assembly in the storage rack and in the limiting case, the fuel assembly that is hit does not undergo any fuel rod failures. This is due to the nature of the spent fuel rack design, where the fuel assembly is recessed into the rack. The energy from the impact is absorbed by the fuel assembly structure and that fuel rod failures (14 failed fuel rods) only occur in the dropped assembly. The FSAR fuel assembly drop is done with a 1280 pound fuel assembly.

I in the case of a drop event involving an underwater lamp,which weighs approximately 80 pounds, it is clearly a non!imiting case and in fact would cause no damage that could result in the release of radioactivity.

Nac r-m mer (s-s2j u

- U t;. NUCLEAR REGULATORY COMMisslON APPROVED LY OMB NO. 3150-0104 (5-92)

EXPIRES: 5/31/95 LICENSEE EVENT REPORT (LER)

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ncc y co WASHINGTON. DC 20655-0001 AND TO TME PAPERWORK REDUCTON PROJECT Q150-0104L OFFICE OF MANAGEMENT AND BUDGET.

WASHINGTON. DC 20503.

FACAITf NAME (1)

DOCKET NUMBER l2)

LER NUMBER HQ PAGE (3)

YEAR hfukra "kfgh N

Millstone Nuclear Power Station Unit 2 05000336 95 - 001 -

00 03 OF 03 TEXT tv more space e raam<ed, une addatorud cpes of NRC Form 366A) (1D The bases of the applicable Technical Specification (3.9.15) states that "the limitations on the storage pool area ventilation system ensures that all radioactive material released from an irradiated fuel assembly will be filtered through the HEPA filters and charcoal absorber prior to discharge to the atmosphere". Since the underwater lamp could not damage a fuel assembly and no radioactive material could be released, the safety significance of this event was minimal.

IV.

Corrective Action

As a result of this event, the Technical Specifications will be reviewed and a series of clarifications and changes will be proposed to provide proper definitions and clear linkage between the licensing analyses and the Technical Specification requirements. Procedures involved with crane operation will be modified to assure that it is clear when the use of the crane is restricted.

i I

V.

Additio.0aunformatiOB There were no failed components i

There were no similar LER's Ells Codes:

i VG - Spent Fuel Pool Ventilation I

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