ML20125B981
| ML20125B981 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 12/26/1979 |
| From: | Mayer L NORTHERN STATES POWER CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| TAC-11094, TAC-11095, NUDOCS 8001020436 | |
| Download: ML20125B981 (16) | |
Text
{{#Wiki_filter:.b l HSEn ' NORTHERN 5TATES POWER COMPANY MI N N E A f*C L l S, M I N N E S OTA 55401 December 26, 1979 Director Office of Nuclear Reactor Reg:21ation US Nuclear Regulatory Commission Washington, DC 20555 j PRAIRIE ISLAND NUCLEAR GENERATING PLANT Docket Nos. 50-282 License Nos. DPR-42 50-306 DPR-60 J Information Relating to Fire Protection Modifications 1 Section 3.1 of the Prairie Island Fire Protection Safety Evaluation Report 1 issued by the NRC Staff on September 6, 1979 requires additional information in the form of design details, test results, or acceptance criteria to be provided to assure that the design of certain modifications is acceptable. Information relating to the following modifications was requested. 3.1.l(1) Auxiliary Feed Pump Area Trench Barrier 3.1.l(2) Penetration Seal Upgrading 3.1.1(4) Foam Seal Upgrading 3.1.4(1) Hydrogen Seal Oil Unit Trench 3.1.4(10) Hatch Area Sprinkler System 3.1.5(1) Protection of Structural Members 3.1.6(1) Combustible Cas Cylinders 3.1.9(1) Timely Containment Fire Suppression Water i 3.1.12(1) Alternate Shutdown Capability 3.1.14(1) Pre-Fire Strar.egies 3.1.18(1) Reactot Coolant Pump Oil Drainage Information concerning items 3.1.l(2) and 3.1.1(4) was provided in our letter dated November 30, 1979, " Evaluation of Penetration Seals and Fire Detectors Required by the Fire Protection Safety Evaluation." Information t,ncerning item 3.1.12(1) was provided in our letters dated October 22, 1979, " Fire Protection Safe Shutdown Reanalysis," and October 23, 1979,
" Fire Protection Safe Shutdown Reanalysis-Transmittal of Cable Routing Drawings." The purpose of this letter is to provide information relating to all of the remaining items listed above. Refer to the attacned descrip- l tive information and drawings. Additional information will be provided !
when available on item 3.1.5(1). j i I 90000032 l i
,. - 8001020 4BC e' l
NORTHERN CTATED POWGR COMPANY' 9 December.26, 1979 Page To permit us to r.omplete these modifications on schedule, we request that any NRC Staf f comments be sent to us by March 1,1980. Please contact us if you have any comments or questions relating to our planned modifications. h' V L 0 Mayer, PE Manager of Nuclear Support Services l LOM/3MM/jh I l cc J G Keppler G Charnoff Attachment 90000033 l l i l
[ t. ) i Attachment Director NRR,~USNRC December 26, 1979-l Information Relating to Fire' Protection Modifications i 3.1.1 (1) Auxiliary Feed Pump Area Trench Barriel We propose to pout a 12" thick slab (see Figures 1, 2, and 3) that .will be 1 offset from the barrier walls, but will be centered under the sliding fire j door. As shown on the figures, the slab will fill the entire trench to i floor level. ], In addition, the trench grating will be covered with a plate from the slab l to.a point approximately two feet outside each of the entrance doors. ) 1 I 3.1.4'(1) Hydrogen Seal 011 Unit Trench We propose to cut.out the concrete around each seal oil unit to form a 6" x 6" trench. This trench will have a grating surface and a slight grade drop to the' turbine room drain. (See Figures 3, 4, and 5.) All
. turbine room drains go to their respective unit sumps located in the condenser pits. The sumps have oil absorbent pillows in them. The sumps ,
are inspected monthly with pillows replaced as necessary. 3.1.4 (10) Hatch Area Sprinkler Svatem The proposed sprinkler addition is shown on Figures 6 and 7. The installation has the approval of American Nuclear Insurers. Material has been received and prefabrication started. Final installation will be completed following NRC Staff approval of the design. During the' January,1980, Unit No. 2 outage, we will tie the system into the main fire header in the Unit No. 2 side of the Auxiliary Building. This must be done to permit completion by October, 1980. 3.1.5 (1) Protection of Structural Members-The project of selecting columns that need protection, procuring an approved coating, and a supplier has been assigned to the NSP Plant Engineering and Construction Department. Application of the retardant will be in accordance with an approved UL or FM design. At this time, a review of materials and vendor qualified procedures is being made. Details of the coating selected and application method will be provided to the NRC Staff by May 1,1980. 3.1.6 (1) Combustible Gas Cylinders
.The use of diamethylomine gas has been discontinued and the gas cylinder removed from the Auxiliary Building.
We are proposing to move the propane cylinder located outside the Cold Lab to a rack located outside the turbine room (see Figure 8). Piping, valves, and fittings from the cylinder to the present penetration into the Cold 90000034
pp
. x I
_ Attachment Director NRR, USNRC December 26, 1979 Lab will be welded steel pipe and will be installed in'accordance with > NFPA-58..
'We have reviewed exterding the above piping into the Auxiliary Building to the Hot Lab to replace the propane cylinder used there. Considering that safety evaluations must be done for.each of'the three penetrations through rated barriers in addition to fire hazard review of. routing gas
-piping through three fire zones containing safe shut-down cabling i and equipment, we have concluded this was_not an' appropriate solution.
We then considered the Hot Lab construction which is a poured concrete region within the Auxiliary Building.- It is a separate fire area protected by a wet pipe sprinkler system. No. safe shut-down equipment or cables are located in the area. - Other flammables, used in the. day to day operation of lab, are present - within the lab so'we propose to' move the propane. cylinder inside this area. Mounting of the tank, piping, and valves will be in accordance with NFPA 58. 3.1.9 (1) Timely Containment Fire Suppression Water At present, fire protection wat;x for use within the containment is isolated during reactor operation. Thid is accomplished by breaking a flanged connection. When fire protection water is required, the connection must be made-up. Following completjon of the containment cooling system modifications and additions now underway, it'will no 1cnger be necessary , to make-up the fire protection system in the containment. - The existing containment fire line will be supplied by a four-inch cross- l connect from the four-inch supply to the CRDM Shroud Cooling Coils. The ; cross-connect will have a capacity of approximately 350 gpm and will be 1 available during plant operations. The cross-connect will include two manually operated four inch gate valves loested within six feet of the personnel access air-lock. The standardd and codes under which all work will be performed, including f abrication cnd instal:.ation, will meet or exceed the existing standards , and codes to 9hich the plant was built. j l The limiting time in pressurizing a containment fire J ine will be only that time reqaired for personnel entry. During the January, 1980, Unit No. 2 outage we will tie the containment fire water line into the cooling system with a tee and isolation valve. The existing fire water supply will therefore be functional until the cooling system modification project is completed next year. 4 1 90000035 1
- Attachment l Director NRR, USNRC:
December 26, 1979 3.1.14 (1) LPre-Fire Strategies ' Attached'are draft copies of fire strategies for the diesel generator rooms. These strategies provide for the isolation of fuel transfer' pumps in the' event ofLfire.- Draft strategies for other plant areas have been-completed and are currently- ' undergoing review by the plant technical staff and operations personnel. .They , will be incorporated in the Operations Manual fire fighting section following . review and incorporation of comments. - 3.1.18 (1) Reactor Coolant Pump Oil Drainage In past discussions with the NRC Staff, we agreed to route' the reactor. coolant pump oil collection' drain piping to sump A.in the basement'of,each containment.
~
In a plant modification made to control radioactive contamination from pump seal water' leakage, oil collection piping was routed from the collection pan outlet 'over and into the nearest floor drain (see Figure 9). All floor + drains are routed to sump A. This installation 'si a slight deviation from the method proposed, but accomplishes the same result using less pipe and reducing the tripping
. hazard in the containment sump area.
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rx _ V_ 4L hlision-Drafc'- p4 ~ FIRE DETECTION 7.ONE 82 J'
' FIRE' AREA N25 LOCATION 695 1cvel #1-Diesel Rm..'EMERG LICHT Yew
- t h Cables Fuel 011 & Lul'a 011?
TYPE OF' FIRE , [~ .2384 lbs 700 gals.
& FIRE LOAD i,
81,910 BTU /sq ft' $ PERSONNEL HAZARDS ~ Acrid smoke from cables lleavy balck smoke from oil'- COMMUNICATIONS. Cait.ronics .page - Sound' powered phonc jackbox. FIRE-EQUIPMENT-Pr.e-action we t pipe system -
.-3 hr fire door-
~
1-1 1/2 hr fire door CO 2 m unted in. room Dry chemical (DC) & hose statfor. outside area EQUIPMENT CONTROL Emerg Gen Pre-lube pump - MCCIT-nus .1 l Emerg Gen Lube oil pump - MCCIT-ilus 1 D-1 Emerg Gen air compressor - Muo1T-Bus,1 121 D-1 Emerg Gen Diesel f uel storage' pmp Panel 134 - Brk 1 122 D-1 Emerg Gen Diesel fuel storagu pump Panel 134 - Brk 2 MCCIT-Bus 1 Bus 110 Brk 113 Secure ventilation to area Loss of diesel room ventilation if MCC is de-energized. Smoke removal by portabic fans necessary if MCCIT-1 is damaged. SPECIAL INSTRUCTIONS Use portable fans for smoke removal Refer to MCC & cell listing for loss of safeguards MCC's-Deluge & sprinkler isolation same as #2 diesel room (see Det Zone 6) . Ensure 121 & 122 diesci fuci stoc..ge pumps I are de-energized. : 1
SUMMARY
The diesel room is provided with flan.e and , , ionization detectors and heat ac tuating devices. A fire would oe immediately i:etectu . ; followed by the pre-action vet pQc nystem hi ing l activated (Det. Zonc 7). CO 2 and hon. stacion. ! are fire fighting. Smoke is the most nazardous element to the fire brigado. l l L 90000049 L L '. t [ u , . - . - - - - _ . - . . -
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uw 9 s M-._ O Extinguisher a Sound powered / gat page Q HeatL activated device . .~ . (J - Ionization detector
$ Flame detector ;( Q i
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t FIRE AREA 26 LOCATION 695 level l#2 Diese} Room EMERG LICilT Yes Cables Fuel Oil & LoLe Oil
-TYPE'0F FIRE' 700 1;als
& FIRE LOAD 244 lbs~ .
'75,366 BTU /Sq ft PERSONNEL HAZARDS Acrid 1 smoke from cables '
. Heavy black smoke from oil Caitronics;page - Sound powered phonc jackbox COMMUNICATIONS Pre-action wet pipe system l FIRE EQUIPMENT 1-3 hr fire door 1-1:1/2 he fire door i
CO2, dry chemical (DC) & hose stati6n out. side area Emerg Con Pre-lube pump - MCCIT-Bus-2 EQUIPMENT CONTROL-Emerg Gen Lube oil pump - MCCIT-3us 2 (' D-2 Emerg Gan air compressor - MCCIT-Bu. 2 123'D-2 Emerg Ccn Diesel-fuel storage pump E Panel 135-Brk 1 124 D-2 Emera, Gen Diesel fuel storaga pump Panel 135-Brk 2 MCCIT-Bus 2 Bus 120 Brk 123 Secure ventil:lation to area Loss of diesel room ventilation if ::CC is de-energized. Snoke removal ty portable } ' fans necessary if MCCIT-2 is camaged. s Use portabic f ans for smoke removat. Ptier 1 SPECIAL INSTRUCTIONS to MCC & cell listing for loss of safe 3;uard's MCC's. Ensure 121 & 122 diesel fuel storage .u:r.ps are de-energized. (:-
SUMMARY
The diesel room is provided with flame sad ionization detectors and heat actuating devic, s. ) A fire would be immediately detected followed by the pre-action wet pipe system beln:; activa:cd (Det. Zone 7). CO and hose statfor. are provided 2 l out side the room to assist in fira fighting. Smoke is the'most hazardous elemeat t i> the fire brigade. j -00cuut 90000051 i Li 4 a qq 4 A._1 -
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-O Extinguisher O' Sound / gat I Page p g Pre -a c tion deluge @
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