IR 05000302/1990022

Insp Repts 50-302/90-22 on 900612-16.Violations Noted But Not Cited.Major Areas Inspected:Review & Witnessing of Integrated Engineered Safeguards & Loss of Offsite Power Tests

ML20055H577
Person / Time
Site:	Crystal River
Issue date:	07/06/1990
From:	Belisle G, Taylor P NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20055H576	List: IR 05000302/1990022 ML20055H575
References
50-302-90-22, NUDOCS 9007270019
Download: ML20055H577 (4)

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' NUCLEAR REGULA10RY COMMISSION ,

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Re' port No :50-302/90-22-e Licensee: Florida Power Corporation 1 3201 34th Street, South, d

~St. Petersburg, FL 33733 j

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Docket No.: 50-302 - License No.: . DPR-72 ,

' Facility Name: Crystal River 3-Inspection Conducted: Jupe 12-16, 1990 i Inspector: HeV II/#M t fatpigne ~ -

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PM.' TafTUf ,

Approvedby:/ N /awh 6 d Z#O l GM. 'BemTe,~ Chief

/'- pteygned

. Test Programs-Engineering Branc ,

Division of Reactor Safety

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SUMMAR ,

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Scope:

4 This routine, ~ announced -inspection was- conducted in the' areas of review and (

witnessing integrated engineered safeguards (ES)= and- loss of offsite power (LOOP) tests.

, EEsults:

R iIn-the areas-inspected, one violation vas identified but is not being cite l

'e - -Inadequate- procedure steps (SP-417) contributed to the reactor building':"--  ;

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emergency cooling fant(AHF-1C) not being in its required position for ES r

. actuation'duringES/ LOOP. test, Train"B"(paragraph 2c)

This licensee identified violation- is .not .being cited because criteri specified in section V.G.1'of the NRC Enforcement Policy were satisfie '

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>, REPORT DETAILS Persons Contactef

- Licensee Employees

• G.- Boldt,J Vice President, Nuclear Production M._Fitzgerald, Supervisor, Nuclear Engineering Services

• R. Fuller, Senior Nuclear Licensing Engineer

• G. Halnon, Assistant Nuclear Shift Supervisor

• H.'Koon, Superintendent, Nuclear' Maintenance

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• W. Marshall, Superintendent, Nuclear Operations .

L *P. McKee,~ Director, Nuclear Plant Operations  !

l * Porter, Nuclear Shift Supervisor

• F. Sullivan, Manager, Nuclear Systems Engineering Other licensee . mployees contacted 'during this inspection included : l engineers, operators, technicians, and administrative personnel, j NRC Resident Inspector-

• P. Holmes-Ray, Senior Resident Inspector L '* Attended exit. interview L IntegratedES/LOOPTest-(61701) 'l L

l Procedure Review

~ The inspector reviewed SP-417, Integrated Plant Response To An ES Actuation, Revision 28, dated June 13, 1990 to verify the following:

L Appropriate levels of management review and approval had been 1 conducted.- l

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The design change (MAR 88-05-24-01)~ requirements which i reassigned selected ES loads to new load blocks and times were l verified to be tested during conduct of SP-41 '

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b ES components. pumps, and ventilation fans required to go to [

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their emergency position during ES actuation with a loss of offsite power were identified in the test steps of the l

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procedur SP-417 contained prerequisites, initial system conditions and !

l precautions to be established prior to conducting the tes Acceptance criteria provided were qualitative or quantitative as appropriate.

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i- 'I The: inspector's comments to SP-417 were presented to the -licensee !

I -and resolved prior to the test J l

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b.- Test Witnessing SP-417 was perfoimed on June 16, 1990.- Prior' to the test. - the l licensee conducted a briefing with plant operators, engineers and ,

electrical technicians assigned to assist in:the performance of the ;

i '. integrated ES/ LOOP test. The briefing was held in a conference roo '

l with the Shift Supervisor leading the discussion. The briefing was a h comprehensive review of the test procedure ~ and covered, in detail, duties and responsibilities required of test personnel, data l acquisition, the operating sequence of- plant systems, and responses to be expected during the tes The inspector observed plant operators establishing prerequisites and j

,. initial conditions for testing Train "A" engineered safeguerd L systems and EDG-1A. These activities, as well as test equipment'

l calibration, were reviewed on a sample basis to verify that procedure requirements were being me The testing of Train "A" started with an ES actuation consisting of a 1 reactor building high pressure si

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l L building pressure signal (30 PSIG)gnal (4 PSIG),

and a simulated high-high'

loss of offsitereactor .

power to the 4160 volt eme'rgency bus. A review of test results I indicated that ES equipment achieved their emergency positions and assigned load blocks, load shedding from the emergency buses had occurred, and the permanent a connected'and auto-connected emergency

~ loads to the EDG 1A did not exceed Technical Specification requirements of 3248 KW. ~The observed load on the EDG-1A 'was approximately 2000 KW. In addition, one of.the new ES logic features was also tested during SP-417. This feature simulated olarge break -

LOCA signals (RCS pressure 500 PSIG) andsverified that the decay-heat'-

. removal pump (DHR-1A) starts and' the emergency.feedwater pump-(EFP-1)

tripped off. The results of this test were satisfactory.

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Following ES/ LOOP testing of Train "A", Train "B", ES systems were aligned and the ES/ LOOP test was performed. The test results for the l Train "B" ES systems ' indicated satisfactory responses. The observed I load on the EDG-1B_ was approximately 1750 KW. It was noted during  !

the first portion of the Train"B" ES/ LOOP test that air handling fan !

(AHF-1C) did not indicate sequencing on after the 4 PSIG reactor building high pressure signal was initiated. A check at the ES I cabinets indicated that AHF-1B had been selected. The selector switch was placed in the AHF-1C position and the response of the fan and its KW load was verified during the ESF/ LOOP portion of the tes ,

The licensee's review indicated that SP-417 procedure steps, wnich I aligned the air handling units, did not adequately address switch I positions for the test and permitted AHF-1B to be selected. AHF-1B

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, was out of service for maintenance. The inspector concluded that th inadequate procedure steps (SP-417 steps 4.4.17.4.2, 4.4.17.4.3, and 4.4.31) was a licensee identified violatio During the exit interview, the licensee stated the following actions were planned or in progress: . Issue a memorandum to the operations groups, discussin the identified procedure problem, and initiate a change to SP-417, identify the procedure problem so root cause analysis can be conducted through the Human Performance Evaluation System. The-inspector had no further question in this are , Exit Interview The inspection scope and results were summarized on June 16, 1990, with those-persons indicated in paragraph 1. The inspector described the' areas inspected and discussed in detail the inspection results listed belo Proprietary information - is not contained in this report. Dissentin ,

comments were not received from the licensee,  ;

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- Inadequate procedure steps (SP-417) contributed to the reactor 1l building emergency cooling fan (AHF-1C) not being-in its required-.

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position-for ES-actuation during ES/ LOOP tests, Train "B" (paragraph-2c). I

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The licensee identified. violation is- not be cited because criteria -

specified in section V.G.1 of the NRC Enforcement Policy were satisfie :!

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