ML19345B281

From kanterella
Jump to navigation Jump to search
Forwards Electrical Cable Penetration Qualification,Fire Pump Capacity Diagram & Safe Shutdown Analysis in Response to Request for Final Disposition of Fire Protection Safety Evaluation Open Items.Encls Available in Central Files Only
ML19345B281
Person / Time
Site: FitzPatrick 
Issue date: 11/20/1980
From: Bayne J
POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To: Ippolito T
Office of Nuclear Reactor Regulation
Shared Package
ML19297A930 List:
References
JPN-80-53, NUDOCS 8011280015
Download: ML19345B281 (4)


Text

.y M

7'/

POWER AUTHORITY OF THE STATE OF NEW YORK y

i-10 Co[JJsapS!plRCLE NEW YORK. N. Y.10o19 i h'n LS 'vHis orCaosT.arany t212, 397.6200

e'.'.*r'i.[a 'clsll.

c, TRUSTEc3 JOHN W UCSTCN

^""$.0d*"

DM MOV 26 !?! !0 5,

\\%My

'"'hiyyg:,

c-a hg aconos c. moAutS

,c,,,,,

,c,,,,,,,

%9 L

,,, c y ri,, y,c, vecs caaismam micw AMO M,

FLYNN ws gem L,,

'~

]iMCES NovemM r 20, 1980

!.*ici"v*cVdise~T

.o car i. Mitu""

r.rocaicic. c'Aaic JPN-8v% 3

!!all.""^~"

THOMAS 4 FREY ss%ica vics.=ssicawr

  • * * " ' " ^ ' * * ' " " '

Director of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D.

C.

20555 Attention:

Mr. Thomas A.

Ippolito Operating Reactors Branch No. 2 Division of Licensing

Subject:

James A. Fit:: Patrick Nuclear Power Plant Docket No. 50-333 NRC Review of Fire Protection Program Safety Evluation Supplementary Items

Dear Sir:

This letter is in response to your October 3, 1980 letter which requested final disposition of those unacceptable (3.2.1 and 3. 2. 8) and incompletc (3.1.9, 3.1.15 and 3.1. 20) items identified, a)

Itc 1 3.1.20 - Electrical Cable Penetration Qualification Electrical cable penetrations are being protected by two basic materials; 1) a RTV Silicone Foam and 2) a RTV Silicone Elastomer.

The fire stop supplier in both cases is TECH-SIL, Inc. of Elk Grove Village, Illinois.

provides a copy of:

a) the NEL-PIA fire stop acceptance form for the RTV silicone foam, b) Test Report TS-TP-0043 of 20 penetration seal configurations and the acceptance of this report by ANI, and c) copies of the TECH-SIL installa-tion instructions from which the Authority has prepared main-tenance procedures.

g S

These documents, upon your review, should resolve this item. ///

b)

Item 3.2.8 - Fire Pump Capacity

$b'O tusI.lo, s

The Authority's letter dated September 5, 1979 (JPN-79-55)73 Q g h,

presented three (3) areas where a single fire pump was not

+o1sc Chs

    • seCA.f) 8 0 i 1 ~" 8 0
r. Ol 5 F

a

. capable of meeting the combined demand for the fixed water suppression systems and 1000 gpm for manual hose streams.

The three areas of concern were a) system 76.5.2.2 - Turbine Building Elevation 272, Zone 2R, b) system 76.5.2.4 - Turbine Building Elevation 272, Zone 1B, and c) system 76.5.2.7 -

Turbine Building Elevation, Zone 1.

Since the three areas are under the turbine operating floor, they are generally considered extra hazard occupancy.

The design as installed had received review and approval by the applicable juris-dictional organization at that time; i.e., NEL-PIA.

At present, per NFPA 13 - section 2-2.1.3,

" Water demand for hydraulically designed systems for protecting extra hazard occupancies or extra hazard portions of other occupancies shall be determined by the authority having jurisdiction", which in this case is the American Nuclear Insurers (ANI).

ANI requires two design points for sprinkler systems under the turbine operating floor:

(1) 0.3 gpm/

sq. ft. over the most remote 3000 sq.

ft.,

and (2) 0.2 gpm/

sq. ft. over the entire area protected by a system, not to exceed 10,000 sq. ft. ANI also recommends a 1000 gpm hose stream allowance.

The three sprinkler zones referenced above are all central fed, wet pipe sprinkler systems, generally using extra hazard pipe schedule.

Per a telephone conversation on November 7, 1980 with Mr. Robert Sawyer, ANI, it was in-dicated that for this type of sprinkler system, an average density design basis is adequate per ANI standards.

This means that the water supply should be capable of providing the average density over the design area, not necessarily main-taining this density at the most remote head.

For example, the flow required to maintain a density of 0.3 gpm/sq. ft.

over the most remote 3000 sq. ft. is 900 gpm (.3 x 3000).

New calculations based on the ANI average density design basis method and, after allowing 1000 gpm for hose streams, show that the three sprinkler systems can provide more than the densities required by ANI.

The resultant densities are:

Zone Required Spray Density Available Avg. Spray (gpm/sq. ft.)

Densit:- (gpm/sq. ft.)

@ area (sq. ft.) after 1000 9pm hose stream allowance 2R (76.5.2.2)

.3

.39 @ 3000 2R (76.5.2.2)

.2

.32 3 4256 (entire area)

)

. ZONE Required Spray D(r

y Available Avg. Spray (gpm/sq. ft.)

Density (gpm /sq. f t. )

@ area (sq. ft.) after 1000 gpm hose stream allowance 1

(76.5.2.7)

.3

.31 @ 3000 1

(76.5.2.7)

.2

.22 @ 7938 (entire area) 1B (76.5.2.4)

.3

.37 @ 3000 1B (76.5.2.4)

.2

.29 @ 5563 (entire area) shows the resultant pump curve versus various design bases and sprinkler zones.

Together with the justification pro-vided in our September 5, 1979 letter, the Authority considers that a single fire pump has the capacity to supply any fixed fire water suppression system plus an adequate reserve for fire hose streams.

c)

Items 3.2.1 - Fire Hazard Analysis 3.1.9 - Alternate Shutdown Capability - Relay Room 3.1.15 - Alternate Shutdown Capability - Cable Spreadina Room is the James A. FitzPatrick Nuclear Power Plant Safe Shutdown Analysis dated September, 1979 and revised as of October, 1981 to reflect the actual modifications being installed in the f acility.

Th.s document of approximately 120 pages should provide the necessar information requested by your October 3, 1980 letter with regard to the above three items.

This analysis and the resultant mod'.fications utilize the guidelines of Appendix A to BTP-APCSB 9.5-1 which was and still is the licensing basis for the above items.

Approximately 75% of the modifications necessitated by the abcve mentioned analysis for these items have already been completed.

Very truly yours, 0Q 1

',4C,[ \\ 'I \\~s, J

Q w c_-

f

\\~ Senior Vice Pf}esident J.'r.

Ba?ne Nuclear Generation

ENCLOSURE 1 ITEM 3.1.20 - ELECTRICAL CABLE PENETRATION QUALIFICATION f

I l

[