ML19290D132

From kanterella
Jump to navigation Jump to search
Submits Transfer of Lead Responsibility for Unresolved Fire Protection on Items Re Fire Pumps & Cable Spreading Room Fire Suppression Sys.Ofc on Nuclear Reactor Regulation Will Evaluate Open Items
ML19290D132
Person / Time
Site: McGuire, Mcguire  Duke Energy icon.png
Issue date: 12/06/1979
From: Reinmuth G
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
To: Moore V
Office of Nuclear Reactor Regulation
Shared Package
ML19290D131 List:
References
IE:RCI-79-03, IE:RCI-79-3, NUDOCS 8002200068
Download: ML19290D132 (4)


Text

-

~

Date: DEC C I373 Serial No.:

IE:RCI-79-03 TRANSFER OF LEAD RESPONSIBILITY

-TO:

Y. A. F$cre, Jr., Acting Assistant Director for Plant Systems, Division of Syst es Safety, h2R S* EJECT: ACCEPTASILITY OF MCGUIRE FIRE PROTECTION SYSTEM J

PISPONSIELE ASSITTAhT DIRECTOR:

G. W. Reircuth, Assistant Director, Division of Reactor Construction Inspection, IE DESCRIFTION OF ITEM REDUIRIha :ESOLUTION:

During the inspection of McGuire 1 & 2 Nuclear Power Plant September 1979 the regicnal inspector identified tr.o unresolved items pertaining to the Permanent Plan: Fire Protection Systems, both of which require evaluation by NER, for proper re. solution.

1.

Fire Pumps Section E.2.(c) cf the licensee's McGuire Nuclear Station Fire Protection Review (FPR) states that the fire pumo installation is desigr.ed to meet the standards develc ed by the !.ational Fire Protection Association (NFPA) where practicable. The "where practicable" statement was apparently acce;ted by NP2 and as such presents inspe: tion proble.s in de ermining

- exactly what the licensee is c:n-itted to. The applicable standard or code for fire pt:a installations is NFPA-20, "Centrifucai rire Pumps."

' wever, the fire prp ins alla: ion at the site does not ree the pr: visions cf NFPA-20 due tc the following:

a.

Tne controller / motor starters for tr o of the three pu :s are located within the turbine building ar.d not acf acent to and within sight of the pu.p mo:crs as required by Section 7-2.1 of NFPA-20.

b.

Tne arrancemer.t of the uter pressure sensing lines between fire protection syste.a and pressure-activated sw'.tches are 1/3 inch in dia:aeter in lieu of 1/2 inch minimu. as specified by Section 7-5.2.1 and Figure A-7-S.2.1 of NFPA-20. Also the water sensing lines are not provided with the required check valves, test connections, and related devices.

I d uu;flMuu[f khI CONTACT:

W. Laudan, IE 49-27551 8002200

V. A. Moore DEC 6 E79 c.

The pump starting circuits from the pressure sensing system which are external from the pump controllers /cotor starters are not electrically supervised, nor arranged such that breakage, disconnecting, shorting of the wires or loss of power to the circuits will cause continuous running of the fire pumps as required by Section 7-5.2.5 of tiFPA-20.

d.

Controllers for two of the three pinps are not listed by Underariters Laboratories, Inc. (UL) or approved by Factory Manual Laboratories, Inc. (FM) for use on electric motor driven fire pumps as required by.

Section 7-1.1.1 of NFPA-20.

Tne fire pu=ps are not provided with labels or otherwise identified to e.

verify that the pumps are actually listed by UL or aoproved by FM for fire pump service as required by Section 2-2 of NFPA-20.

Aopendix D of Supplement 2 to the Safety Evaluation Report of the M:Guire fiuclear Station prepared by ??RR contains the Fire Protection Safety Evaluation Report (FPSER) for the McGuire facility.

Section II.A of the FPSER states that the fire pu n are installed in.accordance with the applicable NFPA guidelines. Th's is not correct as there are a number of features in which the fire pump installation do not reet the applicable NFPA Code (NFFA-20).

Therefore NER should clearly indicate the areas in which the fire pump installation is not recuired to m,eet the provisions of NFPA-20.

2.

Cable Spreading Room Fire Suppression Systems

- A ranually actuated "fc;-type" sprinkler system is installed in ea n cable spreading ro:m.

Section E.3.(c) of the FPR states that sprinkler systems will conform to the requirements of NF?A-13. "Sorinkler Systems," and tiFPA-15 " Water Spray Fixed Systems."

Section F.3.(a).(1) of FFR states that a r.anual wa:er fo; systs is to be provided for each cable spreading room but does not indicate the design requirements of these systems.

The desien and installation requirements are needed in order to assure that the licensee has fulfilled his cox.itments to the NRC.

The water spray systems provided do not meet all of provisions of the NFPA codes and the F?R due to the following:

a.

The systems are designed to discharge water at a density of 0.10 gpm per square foot of floor space whereas Section F.3.(a).l' of the FPR states that the system will be designed to provide a density cf 1.5 gpm per square foot.

Section 404.1.4 of NFPA-15 requires an ir..pingement at a density of 0.15 gpm per square foot directly on the hori: ental or vertical plane centaining the cable trays.

. DEC 6 1979 V. A. Moore b.

The no:21es are arranged to discharge water spray downward and not directly into or on the cable trays as required by Section 4-9.2 of NFPA-15.'

c.

The installed nozzles have a different discharge characteristic (X factor of 4.03) than the nozzles used in the hydraulic calculations (K factor of 2.13). The system design calculations were based on a Grinnel Prctectospray Nor:le D3-21 whereas a model D3-28 was actually installed.

d.

The system is canually activitated whereas Sections 4-4.1.4 and A-4-4.1.4 state that manually cperated systems for cable protection are not effective due to the rapid deterioration of the cable insulation when exacsed to fire.

e.

k'atar Fic, alarm indicators (paddle tyee) are installed on the system side of the con:rol valves. Sectica 3-1.7.3.4 of NFPA-13 prohibits use of this type valve in a dry system since the surge of water when valve is c;ered may seriously da age the waterflow-indicater. -

The water spray fire suppressica systens fer the cable spreading rcces were provided by the iicansee at the reques: of NRR.

It appears that NRR may have civen scri casign guidar.ca on thess systems.

Therefore, the design requirements fcr these sys; ems should be clearly defined so as to be inspectable.

C:05E3 CC'JRSE OF ACT:DN:

RECO:EENDATIONS AN:

1.

NRR will evalu :2 iicensees cent.itments pertaining to Fire Pu:0 installation and Cable Spreiding Roca Fire Suppression System.

2.

NRR will evaluate the present conditicn and determine the acce:tability of existing facili:ies cr pro;0se corrective acticn in compliance witr the NFPA as pr:p:sid by the inspec;or.

3.

IE will pr: vide assistance as necessary and will assure compliance with any ned or revised requirements.

D' "D'W "A

<6.~1 U*7m n

wo vJ

V. A. Moore DEC 6 1979 C0tiCURREliCE:

/

4' j

,/

,j.'

jf *

.. '. W.

/.2- [- 79 G. W. Reinrata, Assistant Director, Division of Reactor Date Construction Inspection, 'IE

-r-- - -

L-fWeM b I?(

V. A. V, core, Jr., Acting ' Assistant Director for Piant Date Systems, Division cf Syster.s Safety, tiRR cc:

R. J. Mat:sta, CSS

0. E. Ve.ssallo, DPM D. G. Eisenhut, CCR
5. A. Yarga, CW R. P. De r.i s e, 0S5 R. H. Vclir,er, CDR J. P. T-ight, 055 R. L. Tedesco, CSS V. Stelic, IE fi. C. M:seley, IE H. D. Thorn':urg, IE
5. E. Eryan, IE n.

n c.

r..
3. H. Grier, RI J. P. O'Reilly, RII J. G. Ke: Pier, RIII
r. V. Seyfrit, RIV R. H. Er.; eiken, RV V,. Terney, F_3A L. V. Gossick, ED0 b'.

Lau:an, IE V. Macre, fiRR C. Murphy, RII

[

L I !

' 11