IR 05000302/1987021

Insp Rept 50-302/87-21 on 870803-07.Violations Noted.Major Areas Inspected:Fire Protection/Prevention & Followup on Previously Identified Insp Items

ML20238A794
Person / Time
Site:	Crystal River
Issue date:	08/21/1987
From:	Conlon T, Harris J, Wiseman G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20238A783	List: IR 05000302/1987021 ML20238A781 ML20238A787
References
50-302-87-21, NUDOCS 8708310214
Download: ML20238A794 (13)

Text

'

.

-

UNITED STATES

/j# Riog% NUCLEAR REGULATORY COMMisslON REGION li

[' n g ,, i *j 101 MARIETTA STREET, * ATLANTA, GEORGI A 30323 -

\...../

I Report No.: 50-302/87-21 Licensee: Florida Power Corporation 320134th Street, South St. Petersburg, FL 33733 Docket No.: 50-302 License No.: DPR-72 Facility Name: Crystal River 3 Inspection Conducted: August 3-7, 198 Inspector p Y / df/ & /

~

~

h Date Zl~Signed S'l 1. R. RiTEman ~~

6 ] A 0] h d 8 'D.- 2 7 Date Signed J.f. Harris ,

Approved by: O 79/ // [DateSigned~ Z [ ~ 87 Tg E. Conlon, Chief Plant Systems Section Division of Reactor Safety SUMMARY Scope: This routine, announced inspection was conducted in the areas of Fire Protection / Prevention and Followup cn Previously Identified Inspection Item Results: One apparent violation was identified - Failure to Implement Fire Protection Procedure TDP-30 B70825 PDR ADOCK 05000302 G PDR

.- .

T

REPORT DETAILS Persons Contacted Licensee-Employees R. A. - Arnold, Nuclear Training Instructor .

• G. A. Becker,. Manager Site Nuclear Engineering Services .

*W. K. Bandlaver, Assistant Nuclear Plant - Operations Manager

• C. Brown,-Manager of,0utages .

• M.' E. Collins, Nuclear. Safety & Reliability Superintendent

• W. P. E11sberry, Nuclear Operations Training Supervisor

• R. E. Fuller,' Senior Nuclear Licensing Engineer 3

' *D. V. Harper.1 Licensing Assistant '

• S. G. Johnsan, Manager Site Nuclear Services

!

• M. W. Kirk, Nuclear Operations Engineer

.* M. S. Mann, Nuclear Compliance Specialist .,

'

• L. W. Moffatt, Nuclear Safety .

• W. L.- Rossfeld, Nuclear Compliance Manager

• J. L. Russell, Senior Fire Protection Specialist

• E. E. Welch, Manager, Nuclear Electrical /I&C Engineering Services

• K. R. Wilson, Manager, Site Nuclear Licensing i

Other Organizations

• H..S. Howard, Howard and Associates NRC Resident Inspectors  ;

• T. Stetka, Senior Resident Inspector

• J. G. Tedrow, Resident Inspector  !

• Attended exit interview Exit Interview The inspection scope and findf ags were summarized on August 7,1987, with-those persons indicated in paragraph I above. The inspector described the

,

areas inspected and discussed in detail the inspection findings. No dissenting comments were received from the licensee. The following item

} was identified daring this inspection.

l p

Violation Item (302/87-21-01), Failure to Implement Fire Protection Procedure TDP-307 - Paragraph 5.e.(2).

The licensee did not identify as proprietary any of the inaterials provided to or reviewed by the inspector during this inspectio L - - _ - - - - _ - - _ _ _ _ _ _ - - - _ _ _ _ - - - --_o

__

-

.

3. Licensee Action on Previous Enforcement Matters (Closed) Violation Item (50-302/84-34-03), Inadequate Procedures for Performing Specified Requirements: The corrective actions outlined in Florida Power Corporation's (FPC's) response to the second example of this violation, dated January 22, 1985, were reviewed by the inspectors. The first example of the violation related to Procedure SP-157 was denied by the licensee and this denial was accepted by the NRC Regional Staff. The second example involved WR No. 5253 The inspectors verified that a list of the safety-related breakers was developed, attached to the QEIP-01 inspections, and incorporated in the final work package. Additionally, the inspectors reviewed the documented signoff of the Quality Group inspections for the safety-related breakers on the 4160V engineered safeguards buses 3A and 3 This documentation appeared adequate to document the QEIP-01 inspections. Based on these reviews, it appears that the licensee's corrective actions were adequate; therefore, this item is close i (Closed) Unresolve.d Item (50-302/85-30-10), NRR Peview and Approval of Appendix R Emergency Lighting: Section III.J requires emergency lighting units with at least 8-hour battery pow..r supply to be provided in all areas needed for operation of safe shutdown equipment and in access and egress rouus thereto. The installation and arrangement of the installed lighting units were reviewed by NRC inspectors during the 1985 Appendix R review and found to meet Appendix R,Section III.J; however, battery powered emergency lighting units were not provided in a number of plant areas in which operators verify shutdown component operability, valve alignment, etc. and for operator actions which may be required due to spurious operations. For these plant areas, the plant operators use the existing permanently installed emergency lighting system supplied from the emergency diesel generators and from lighting supplemented by portable hand lights. The portable hand lights are maintained in designated sterage cabinets located in the remote shutdown panel room, auxiliary building nuclear operators office on 95' elevation, and turbine building operators office on 119' elevatio By letter, dated July 25, 1985, from G. R. Westafer, FPC to J. F. Stolz, NRC/NRR, FPC provided an evaluation and justification for the existing emergency lighting system for NRC/NRR review and approva By letter to NRR dated July 17, 1987, FPC provided supplemental information to the staff concerning emergency lighting for remedial

'

actions during remote shutdown for a fire even Additional commitments for shutdown procedure revisions and clarifications were ,

made in this correspondence. Based on the licensee's additional j commitments to NRR, this item is close ]

4. Unresolved Items j i

Unresolved items were not identified during this inspection, j l

l l

_ _ _ - - - _ - - - - - - - _ _ - - - - - - - - - - - - - -- -- u

_

.

.

l

1 1 5. Fire Protection / Prevention Program (64704) t Fire Prevention / Administrative Control Procedures The inspectors reviewed the following Fire Prevention / Administrative Procedures:

AI-200 Rev. 1, May 19, 1986 Guidelines for Handling Use and Control of Transient Combustibles .

AI-2205 Rev. 4, March 30, 1987 Administration of Fire Brigade Organization EM-210 Rev. 2, July 22, 1987 Duties of the Environmental Survey Team

.

TDP-307 307 Rev. 7, November 11, 1986 and Intermin Change l'

June 3, 1987 Nuclear Emergency Team Training Program Section 6.4 Fire Brigade (F. 8.)

6.5 Fire Brigade Tean Leader 7.4 Appendix 4 - F. B. Training 7.5 Appendix 5 - FTL Training CP-137 Rev. 6 July 1, 1987 Fire Barrier Penetration Breach Report CP-118 Rev. 16, September 5, 1986 Fire Prevention Work Permit Procedure CP-113 Rev. 52, January 20, 1987 1 Handling and Controlling Work Requests and Work Packages Based on this review, it appears that the above procedures meet the NRC guidelines of the document entitled " Nuclear Plant Fire Protection Functional Responsibilities, Administrative Controls, and Quality Assurance," dated June 197 Fire Protection Surveillance Procedures ,.

The inspectors reviewed the following Fire Protection System Surveillance Procedures:

- SP-338, Remote Shutdown Panel Operability Verification Revision 7, June 22, 198 !

- SP-364, Fire Hose House, Hose Reel Station, and Fire Cart Inventory, Revision 23, April 7,198 !

_ . _ _ -

-

f- .

t l 4

- SP-366, Fire System Annual Valve Surveillance, Revision 20 June 27, 198 ;

- SP-4048, Control Complex, Auxiliary and Intermediate Buildings  !

Circuitry Check, Revision 2, May 18, 198 l

- SP-404C, Control Complex. Auxiliary and Intennediate Buildings '

Fire Service Sprinkler Mechanical Check, Revision 0, June 26, 198 SP-501A, Halon ASC Weight and Pressure Check, Revision 1, '

June 9, 198 '

-

SP-501B, Halon System Function Check, Revision 0, February 19, 198 SP-802, Annual Fire Hose Hydro Test and Hose Reel Inspection, Revision 14, September 2, 198 The above surveillance procedures were reviewed to determine if the various test outlines and inspection . instructions adequately implement the surveillance requirements of the plant's Fire Protection Technical Specifications. In addition, these procedures were reviewed to determine if the inspection and test instructions followed general industry fire protection practices, NRC fire protection program guidelines and the guidelines of the National fire Protection Association (NFPA) Fire Codes. Based on this review, it appears that the above procedures are satisfactor c. Fire Protection System Surveillance Inspections and Tests The inspectors reviewed the following surveillance inspection and test records for the dates indicated:

SP-4048, Control Complex, Auxiliary and Intermediate Buildi Circuitry Check (Annual) - March 12, 1986 and May 27, 1987 SP-501A, Halon ASC Weight and Pressure Check (Semiannual;y)

- April 11, 1986, October 9,1986, April 2,1987 SP-501B, Halon System Functional Test (18 Months) January 21, 1987 The surveillance test record data and testing frequency associated with the above fire protection system surveillance test / inspections were found to be satisfactory with regard to meeting the requirements of the plant's Fire Protection Technical Specification . _ _ - _ __ _ - - _ - _ _ _ _ - _ _ _ -

..

.

.

.

.

l

,a -

!

5 Fire Protection Audits The most recent audit reports of the-Crystal River 3 Fire Protection program were reviewed. The audits were:

Audit Report QP-276, September. 23, 1985 to October 16, 198 This report was closed by licensee letter, dated October 14, 1986. All outstanding issues had been satisfactorily resolve Audit Report QP-292, July 14,1986 to August 1, .198 Nine specific audit findings were identifie Three areas of concern

_w ere. discusse The licensee has either implemented corrective , actions associated with these audit findings or has scheduled an action completion,date for corrective action The licensee appears ~ to be taking the appropriate corrective actions on these audits- findings, e. _ Fire Brigade (1) Organization Tha ~ fire brigade is composed of approximately 81 personnel from the plant staf The on-duty fire brigade team consists of a fire team leadce and.four brigade members. The fire team leader is normally the Nuclear Assistant Shift Supervisor and the remaining fire brigade members are composed of Operations and Building Services personne The inspector reviewed the

" Control Center 1.og" for the period: July 1, 1987 through August 4, 1987, and verified that_ sufficient fire brigade personnel were assigned to each on-duty shift to meet the provisions of Technical Specification 6. (2) Training Procedure TDP-307 outlines the fire brigade training progra Each fire brigade member receives fire brigade initial training which is designed to provide basic knowledge and manual fire fighting skill The initial fire brigade training program is  ;

approximately 44 hours5.092593e-4 days <br />0.0122 hours <br />7.275132e-5 weeks <br />1.6742e-5 months <br /> in duration and includes 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of  !

classroom training,16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> of hands-on-training at the Florida State Fire College and a four hour plant familiarization sessio The inspectors reviewed the licensee's initial fire brigade training program to verify that the following training topics are being covered:

- Indoctrination of the plant fi re fighting plan with specific identification of each individuals'

responsibilities.

! - - - - - - - - - - - - - - _ - - - - - - - -

_ _ _ _ _ __ _ . - _ _ -.. -

_ _ _ . _ . . - _ _ . _ . . _ - - -

' ; .

'!

m

- Identification of- the type and location of fire hazards and -

associated types of. fires that could occur in-the plan The toxic and corrosive characteristics of expected

_ products of combustio Identification of the location ~ of fire fighting equipment i for each fire area and familiarization with the-layout .of

'the plant, including' access and egress routes'to each are :The proper use of available fire fighting equipment.and the .

correct method of fighting each type of. fire. The types o fires 1 include; fires in energized' electrical equipment,-

fires- in cables and cable trays, hydrogen fires,: fires involving flaninable' and combustible liquids or hazardous process chemicals, fire resulting from . construction or

'

modifications (welding), and record file fire The proper use of communication, lighting ventilation'and emergency. breathing equipnen l

- The proper method for fighting fires inside buildings' and

,"

confined spaces.'

- The. direction 'and coordination of the fire fighting activities (fire brigade leaders only).

- Detailed review of fire fighting strategies and procedure Review of the latest plant modifications and corresponding -

changes in fire fighting plan Based on this review, it appears that- the licensee's initial

.

fire brigade training program covers the above required training topic In addition, it appears that the licensee's fire brigade training program repeats the basic fire fighting skills of the initial program to qualified fire brigade members.every j two year j In addition, the' inspectors reviewed the training and drill ,

records for 14 fire brigade and team leaders for 1986 and 1987 .(

and found that two of the fire brigade members had not completed I all quarterly requalification training in 1987 for the purpose  !

of qualifying as a' fire team member as required by Section 6. of procedure TOP-30 The inspectors verified that these ,

individuals were assigned on-shift fire brigade duty during 1 July 198 This is identified as Violation Item (50-302/87-21-01), Failure to Implement Fire Protection Procedure TDP-30 L

-

.

'

l The review also indicated that the shift fire brigade leaders '

had completed all required initial, requalification training and brigade leadership trainin (3)- Fire Brigade Fire Fighting Strategie I The inspectors reviewed fire fighting strategies (Pre-Fire-Plans)

for the following plant areas:

i

'

AB-95-6 AB-95-12 AB-95-8 Based on this review, the inspectors determined that the above fire fighting strategies adequately addressed the fire hazards l in the area, the type of fire extinguishants to be utilized, the i direction of attack, systems in the room / area to be managed in I order to reduce fire damage, heat sensitive equipment in the room / area, and specific fire brigade duties with regard to smoke ,

control and salvag f (4) Fire Brigade Equipment The inspector performed an inspection of the fire brigade equipment consisting of turnout gear (coats, boots, gloves, 4 helmets, etc.) and the self contained breathing apparatus (SCBAs) stored .at the fire ' brigade response location on 95'

elevation of the turbine buildin ,

Additional turnout gear and fire fighting equipment such as fire hose and nozzles, lanterns, extra air bottles, and portable exhaust fans are stored on two fire carts located in the I auxiliary building (Elevation 119') and turbine building ;

(Elevation 145').

Based on this inspection, the designated inventory of fire brigade equipment stored at the fire brigade response locations

'

and on fire carts appeared to be properly maintained and stored in a ready conditio . Plant Tour and Inspection of Fire Protection Equipment Fire Service Water Supply and Outside Fire Protection Walkdow The inspectors verified that the two CR-3 service water storage tanks were in service and met the requirements of the Technical Specifications. The two diesel engine driven and one electric motor driven fire pumps were inspected and found to be inservice. The !

inspection verified that the fire service 30 gpm motor-driven jockey pressure maintenance pump was maintaining a minimum 110 psi in the fire service syste I

____ The following sectional isolation / control valves in the outside fire protection water supply system were inspected . and verified to be properly aligned.and sealed in position:

FSV-3' -

Fire Protection Water Tank 1A Isolation-Valve FSV-31 -

Fire Protection Water Tank 1B Isolation' Valve l

'

FSV-125- - Hydrant. Isolation Valve The following fire hydrants and fire hydrant equipment houses were inspected:

Fire Hydrant Hose House FH-3 Fire Hydrant Hose House FH-4 Fire Hydrant Hose House FH-5 The equipment ' houses contained the minimum equipment requirement of that specified by' NFPA-24, Private Fire Service Mains' and Their Appurtenances, and/or the FSAR commitments, The equipment appeared to be adequately maintaine A tour of the exterior of the plant indicated that suff1(cient clearance was provided between permanent safety-related buildings and struc:ures and temporary buildirigs, trailers, and other transient combustible materials. The general housekeeping of the' areas adjacent to the permanent plant structures was satisfactory, Permanent Plant Fire Protection Features A plant tour was made by the inspectors. During the plant tour, the following safe shutdown related plant areas and their related fire protection features were inspected:

- Control Complex - Main Control Room / Fire Area CC-145-118B  !

- Control Complex - Cable Spreading Room / Fire Area CC-134-118A

- Auxiliary Building Elevation 951'/ Fire Area 3

- Auxiliary Building - Elevation 119'/ Fire Area 6

-

Auxiliary Building - Elevation 119'

Diesel Generator Rooms Fire Area AB-119-7A Fire Area AB-119-78

- Intermediate Building - Elevation 95'/ Fire Zone IB-95-200C

.The fire / smoke detection systems, manual fire fighting equipment (i.e., portable extinguishers, hose stations, etc.) and the fire area boundary walls, floors and ceilings associated with the above plant areas were inspected and verified to be in service or functiona Based on this inspection, it appears that the fire protection features associated with the above plant areas are satisfactorily h maintained, except there appeared to be a number of Maintenance Deficiency Tags identified on Fire Protection Equipment. These conditions will be reviewed further by the site Resident Inspector '!

i

._ _ _ _ _ - _ _ _ _ _ - _ _ _ _ _ - _ _ _ _ _ _ . _

.-- - _ _ _ _ - _ -

-

.

The plant tours also verified the licensee's implementation of the fire prevention administrative procedure The control of combustible and flammable materials, liquids and gases, and the general housekeeping were found to be satisfactory in the area inspecte Except as noted above, no additional violations or deviations were identified in the areas inspecte . Inspector Followup Items (IFI) (Closed) IFI (85-30-02), Technical Specifications Required for New Remote Shutdown Panel:

FPC's letter of August 30, 1984, from G. R. Westafer to H. R. Denton, NRC/NRR requested an amendment to the Technical Specification to revise the existing Section 3.3.3.5, Remote Shutdown Instrumentation, to include data on the new remote shutdown panel which was installed during Refueling Cycle V (Technical Specification Change Request No. 124).

On July 3, 1486, the NRC issued Amendment No. 75 to the Crystal River Operating License which restricted this requested change to only indicate that the previous instrumentation was relocated to the new remote shutdown panel. Other features of the new remote shutdown panel such as transfer switches were not incorporated into the revised Technical Specificatio By letter, dated December 19, 1985, FPC withdrew Technical Specifi-cation Request No.124 and indicated that it will be addressed during implementation of the CR-3 Technical Specification Improvement Project (TSIP) which is being tracked by the Babcock and Wilcox Owners grou Based on this action, this item is close (Closed) IFI (85-30-06), Review of Licensee's Corrective Actions for NCOR No. 85-130:

On July 19, 1985, the licensee identified a number of plant areas primarily within the control building, which could not be reached by less than 100 feet of 1-1/2-inch fire hose. Operating license paragraph 2.C.(9) states that the licensee is- required to complete the modification identified by paragraph 3.1 through 3.31 of the Fire Protection Safety Evaluation Report (SER), dated July 27, 1979. If these modifications were not to be completed, a report explaining the circumstances was to be submitted to the NR SER paragraph 3.24 required the licensee to verify that all safety-related areas of the plant including the control complex could be reached with at least one effective hose stream utilizing no more than 100 feet of hos Apparently this verification was not accomplishe l

_ _ _ - - - _ - - - _ - _ - 1

_ _ -. __

(

.

,

The inadequate interior fire hose station coverage was identified by the licensee and documented by Nonconforming Operational Report (NCOR) No.85-130. This discrepancy was identified to the NRC by letter report, dated December 19, 1985. This letter submitted a fire protection engineering evaluation for resolution of the issue which justifies the addition of fire hose to certain hose stations within the plant. These calculations indicate that an effective hose stream will be provided from any hose station using 150 feet of hose. FPC has added hose to the following stations to reach safety-related areas:

FSV - 155 Elevation 145' Entrance to Control Complex FSV - 170 Elevation 95' Intermediate Building - FW Pumps FSV - 134 Elevation 119' Intermediate Building -

Containment Personnel Airlock FSV - 135 Elevation 95' Auxiliary Building -

Corridor Outside Chem-Rad FSV - 143 Elevation 95' Auxiliary Building - ES MCC 3Al FSV - 138 Elevation 95' Auxiliary Building - Elevator FSV - 139 Elevation 95' Sea Water Room FSV - 137 Elevation 119' Auxiliary Building - Elevator FSV - 142 Elevation 119' Auxiliary Building - ES MCC 3AB FSV -136 Elevation 162' Elevator FSV - 133 Elevation 162' Auxiliary Building - North of Spent Fuel Pools i Based on the inspector's review of the licensee's corrective actions

'

these appear adequate to close out this ite (Closed) IFI (85-30-07), Examine the Reliability of the Motor Overload Heater Element Trip Devices as 0pposed to a Magnetic Trip Circuit Breaker fer RB Fan No. 3B:

The overload heaters are now used for long time overcurrent

,

conditions and a magnetic circuit breaker has been installed to insure breaker coordination and preclude relay racing. This item is l

close d. (Closed) IFI (85-30-08), Review of Implementation and Training for AP-880: >

The inspectors reviewed Procedure AP-880, Revision 4, dated June 9, 1986. Training records reviewed by the inspector's indicated that Requalification Training for operations staff on AP-880 was implemented on February 27, 1986. The training consisted of a one hour class on shift. Based on completion of this training, this item is closed.

l

l l

l

}

_ - _ _ - _ - _ .

-

.

11 e. (Closed) IFI (85-30-09), Review of Communications and Area Access for ,

Control Room Evacuation:

This item was identified during a NRC Appendix R fire protection walkthrough. The radio equipment and room access keys were stored in an area where a fire event would require their use, but where they may have not been available. On October 15, 1986, the licensee relocated the access keys and transfer keys for the Remote Shutdown l Panel rooms to a lock box located outside the room. In addition, a portable radio and charger was installed in the remote shutdown panel room on April 25, 1986, to be used for operations communications in a fire event. The inspectors reviewed surveillance procedure SP-338 Rev. 4, dated June 24, 1986, which provides verification of the operability of this equipmen The inspectors verified that the access key box and radio communication equipment was in-place at the remote shutdown panel room. Based on this review, this item is closed, f. (Closed) IFI (86-29-01), Review of Licensee's Corrective Actions for Poor Housekeeping in Radwaste Decontamination Areas Identified by SP-809:

This item concerned poor housekeeping in the laydown area of 143'

plant elevation. The work in this area was associated with extensive maintenance and rebuilding of the waste compactor by contractor personnel. The licensee initiated corrective actions by placing a FPC supervisor in charge of coordinating the cleanup of the area with the site contracto The inspector reviewed the licensee's surveillance SP-809 records for September 1986 which indicated the area had been cleaned. Based on this review, this item is close g. (Closed) IFI (86-29-02), Degradation of TSI Fire Barrier Enclosures The inspector noted that some of the TSI barrier material within fire area CC-124-116 and fire zone 18-95-200C appeared to be leaking moisture and in some areas was flaking from he surface of the assembl The licensee stated this condition had been previously identified and that the vendor had been requested to come to the site to review the cause of the condition. The licensee stated that TSI had indicated that this condition did not degrade the fire resistive properties of the barrier enclosure, but that the condition needed further revie Field inspections by Site Nuclear Engineering Services (SNES) and Thermal Science Inc. (TSI) representatives concluded that barrier appearance changes were caused by sources of moisture not associated with the barrie Corrections to areas of concern were performed under Work Request 82950 and 82164. Thermal Gravimetric Analyses were also performed on the material to determine if there was a degradation of the thermal properties of the barrier materia ._ _ _ _ _ _ - _ _ _ _ - _ _ _ _ _ -

___

- ..

i

Results of this testing showed that there were no changes in the thermal properties of the sample. During this inspection, the NRC inspectors walked down the area of concern and verified that repairs had been made. During the inspection, the inspectors noticed that there were still some minor problems with moisture which indicated that surveillance will have to be made to verify that the material is not being degraded. This item is close h. (Closed) IFI (50-302/86-36-01), Storage of Coating Materials Per Manufacturers Recommendation:

Examination of storage controls indicated that coating materials were being stored in a level C which does not have any temperature controls. Review of manufacturer's technical bulletins for coatings being supplied to the licensee indicated coatings should be stored at 70 Inspection of the coatings storage area during this inspection indicated that coatings are now being stored in a temperature control-led environment that meets manufactures requirement This item is closed, i

i

_ _ _ _ _ _ - _ - _ _ - _ _ _ _ _ _ _ - -

b