ML19345E794
| ML19345E794 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 01/05/1981 |
| From: | Pasternak R POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK |
| To: | Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| IEB-80-24, JAFP-81-001, NUDOCS 8102060147 | |
| Download: ML19345E794 (7) | |
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POWER AUTHORITY OF THE STATE OF NEW YORK JAMES A. FITzPATRick NUCLEAR POWER PLANT S
RAYMOND J pASTERNAK P.O. BOX 41 Re:Went Meneger Lycoming. New York 13093 31s-342-3840 January 5, 1981 SERIAL: JAFP-81-001 e
d I
Boyce H. Grier, Director 2
ggB1".O United States Nuclear Regulatory Commission I{
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<*n 7 Region 1 go e 11 631 Park Avenue es King of Prussia, PA 19406 4/
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SUBJECT:
NRC ISE BULLETIN NO. 80-24 PREVENTICN OF DAMAGE DUE TO WATER LEAKAGE INSIDE C0tlTAINMENT
Dear Mr. Grier:
to this letter describes the cooling water system present inside the FitzPatrick containment, which the JAFNPP Interprets as being a closed system. is the operating diagram for the Reactor Building Cooling System which shows the schematic arrangement of piping, valves, containment penetrations and components supplied.
Very truly yoe s,
/
RJP:WF:nvw RAYMOND J. PASTERNAK Enclosures RESIDENT MANAGER cc:
Director NRC Office of Inspection & Enforcement Subscribed and Sworn to before Washington, D.C. 20555 me this 5th day of January, 1981 George T. Berry, PASNY, NYO L
/t a r; n a J. P. Bayne, PASNY, NYO m {yg,p g g Notary Public G. M. Wilverding, PASNY, NY0 R. Ram, PASNY, NYO Notary pese. state of flew York M. C. Cosgrove, PASNY, JAF (w/o Enc. 2)
Appoir.ted in osweso county W. Fernandez, PASNY, JAF (w/o Enc. 2)
My Commluion Expires March ao,19 Egj D. E. Tal1, PASNY, JAF (w/o Enc. 2)
NRC Resident inspector Document Control Center (w/o. Enc. 2)
NRCB-80-24 Filo (w/o Enc. 2) 8102060 \\tn
Boyc2 H. Gricr, Director Jrnu ry 5, 1981 U.S. Nuctscr Regulatory Commission JAFP-81-001
SUBJECT:
NRC isE BULLETIN 80-24 ENCLOSURE 1 - Paga 1.
la.
Discussion of containment cooling system inside drywell, Ref.
Figure OP-40-1.
The component cooler assemblies located in the drywell consist of drywell cooling assemblies A & B, drywell equipment sump cooler, recirculation pumps A & B motor _inding and bearing coolers, and recirculation pump A & 8 pump bearing and seal coolers.
During routine operation, Reactor Building Cooling (RBC) supplies containment cooling.
RBC is a closed system with the demineralized water system providing makeup from 3 tanks with a total capacity of 75,000 gallons. Automatic makeup to the RBC head tank from the demineralized water header is monitored by an in-line flow recorder, 15-FR-111, with makeup water requirement logged weekly on F-ST-400.
Rd' has provisions to be supplied from the Emergency Service Water (ESW) system during conditions discussed below.
If the ESW return valve from RBC is not fully shut, makeup to the RBC head tank is inter-locked shut.
During a LOCA, RBC will continue to supply containment cooling.
If RBC system pressure, as sensed on the P.BC pump discharge by 15-PS-122A-D, decreases to 40 psig, ESW pumps will automatically start and ESW supply and return valves, 46-MOV-101A & B and 15-MOV-175A
& B will open to inject raw water to RBC.
The recirculation pump and motor coolers wculd be automatically supplied by ESW.
ESW would not automatically be supplied to the drywell cooling assemblies or the equipment sump cooler because isolation valves 15-MOV-102 and 103, are normally shut.
I f 15-MOV-102,103,175A or B, or 46-MOV-101 A or B were inadvertently opened during routine operations, RBC flow to ESW would be blocked by check valves seating on the higher RBC pressure.
Therefore, RBC can be considered a closed system during routine operation, i.e., RBC supplying water fer containment cooling and cooling for equipment in the containment.
In the off-normal case, i.e., loss of RBC pressure, the recirculation pump and motor coolers would be the only components inside containment automatically supplied by ESW.
Operator action is required to supply ESW to the drywell cooler assemblies and the equipment sump cooler.
ESW is an open system taking suction from the intake structure and discharging to the normal service water discharge.
Assuming the worst case of a leak into the containment from a cooler or associated piping while ESW was supplying all components with cooling water the following methods are installed for leak detection:
4 1.
Recirculation pump A/B seal cooling water flow icw, 1 0 GPM, on RBC return line. Annunciators on panel 9-4 and computer alarm.
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_ Jcnuary 5,1981.
Boyes H. Grior, Directsr U.S. Nuclocr Regulctory Commission JAFP-81-001 SU6 JECT: NRC l&E BULLETIN 80-24 ENCLOSURE 1 - Paga 2.
i 2.
Recirculation pump A/B motor winding cooler water low flow 5,140 GPM, on RBC return line.
Annunciators on panel 9-4 and computer alarm.
3.
Recirculation pump A/B cooling water low, on RBC combined i
return line.
Computer alarm only.
4.
RBC outiet drywell coolers A/B flow low 5)50 GPM. Annunciators on panel 9-75 and computer alarm.
5.
RBC to drywell equipment sump cooler flow low f)0 GPM.
Annunciator on panel 9-4 and computer alarm.
6.
Recirculation pump motors A & B cooling water leakage,
=6 ounces. Annunciators on panel 9-4 and computer alarm.
7 Drywell floor sump Hi-HI (+42") or Lo-Lo, second (backup) pump automatically starts.
Annunciator on panel 9-4 and computer alarm.
a 8.
Drywell equipment sump high temperature / low cooling water flow, Indicates either low cooling water flow (same as
- 5)/ fill with hot leakage.
Annunciator on panel 9-4 and computer alarm.
9 Drywell floor drain sump leakage, indicates that floor drain pump 20P-1A or B is running and sump pump out timer has' run for >5.5 minutes or sump fill timer has been off
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for 5,80 minutes indicating too fast fill. Annunciator on panel 9-4.
10.
Drywell equipment sump level Hi-Hi (+42") or.Lo-Lo, i
indicates second (backup) pump automatically starts.
I Annunciator on panel 9-4.
11.
Drywell equipment sump leakage, provided equipment pump Isolation valve is open, indicates that with one pump running the sump pump out timer has been running for >6 minutes or sump fill timer has been off for <20 minutes indicating' too fast fill. Annunciator on panel 9-4.
12.
Recirculation pump A or B motor bearing oil HI/Lo level, could indicate water to oli leakage.
Annunciator on panel 9-4.
13 Drywell equipment sump or floor drain sump rate of rise Hl. Indicates abnormal increase in rate of sump filling.
Annunciator on panel 9-4.
14.
Recirculation pump motor high temperature, Indicates a potential loss of cooling water to recirculation pumps.
Annunciator on panel 9-4.
I F-SP-21, Loss of RBC, the first step of the immediale Action is to scram the reactor manually and carry out A
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Boyc3 H. Gricr, Dircct:r Jrnuary 5, 1981
.U.S. Nuc1ccr R gulctory Commission JAFP-81-001
SUBJECT:
NRC l&E BULLETIN 80-24 ENCLOSURE 1 - Ptga 3 F-SP-25 (Reactor Scram).
Subsequent operator action is to determine why the system was lost. A leak from RBC into containment could readily be pinpointed using the above annunciators, system display and metering indication.
Technical Specification 3.6.D and Table 3 2-5 requires the drywell equipment drain sump flow integrator and the floor drain sump flow Integrators to be operable any time fuel is in the vessel and coolant temperature is >212 F.
1.
Reactor coolant leak rate inside containment shall be established once/ day utIIIzing the equipment and floor drain sump systems.
Leakage from unidentified sources shall not exceed 5 GPM and total reactor coolant system leakage shall not exceed 25 GPM.
Reference Technical Specification Section 3.6.D.1.
2.
The reactor coolant leakage detection system shall be operable during reactor operation.
From and after the time that either the equipment drain pump or floor drain pump subsystems is made or found to be inoperable for any reason, reactor operation is permitted for the succeeding seven (7) days.
From and after the time that a redundant component of either subsystem is found to be Inoperable for any reason, continued reactor operation is permissible for the succeeding thirty (30) days.
Reference Technical Specification Section 3.6.D.2.
3 In addition, unidentified leakage is monitored as required by Bulletins 74-10, 10A and 108..This monitoring would detect small leaks in the RBC system within containment.
In view of the above, JAFNPP would easily detect small volumes of leakage from the RBC system during routine reactor operation.
If ESW were used to supply RBC equipment in containment, the reactor would have been shutdown as required by F-SP-21 and leakage would still be easily detected within the Ilmits/ requirements of Technical Specification and/or Bulletins 74-10, 10A and 108.
Ib & i. Source of water chemical content, and detection of radioactive contamination.
RBC is supplied from the demineralized water header.
It is continuously monitored for conductivity (15-CIS-112), with an alarm at 5 pmhos; and radiation (17-RA-352), with gross beta and gamma Hi, Hi-HI and downscale alarms. Annunciators are on panels 9-3 and 9-6. In general, weekly samples are taken on BBC and analyzed for the following:
conductivity - 3 0 pmho/cm max 5-9 pH 500 ppb max C1 0.5 ppm max 0
2
LEGO W. WUOv, WITUmW ajocuovg m s U.S. Nuc1 car Regulatory Commission JAFP-81-001 SUBJECT : NRC ISE BULLETIN 80-24 ENCLOSURE 1 - Pags 4.
ESW utilizes lake water.
It is continuously monitored for gross beta and gamma at the service water effluent.
17-RM-351 provides Hi, Hi-Hi, and downscale alarm functions annunciated on panel 9-3 ESW water typical analysis follows:
conductivity
- 300-600 pmho/cm pH
- 7 7 - 8.7 C1 65 ppm TDS
- 150 - 400 ppm An inadvertent introduction of ESW to RBCLC would be readily detected by rise in conductivity and associated annunciator.
c.
Piping and cooler materials:
1)
RBC piping is class 151, 150# carbon steel.
2)
Drywell cooler assemblies have copper tubes SAE 75, 250# test.
3)
Drywell equipment sump cooler is 316 SS.
4)
Recirculation pump motor winding and bearing coolers have copper / nickel tubes and carbon steel headers.
5)
Recirculation pump bearing and seal coolers are 304 SS.
d&e. History of cooling water system leakage and repairs:
1)
ANA-227066 -
6-29-74 2)
ANA-292703 -
RBC return 1Ine flange from 02-P-1B leak.
6-24-74 Flange bolts were loose.
3)
ANA-260545 -
Motor cooling water leakage alarm -removal of 2-7-75 1/2" plug at base of switch housing revealed about 6 oz. accumulation probably due to condensation, af ter removal alarm cleared.
4)
WR10900 -
Replaced partially failed equipment drain sump 8-3-78 cooler with new design (modification F1-78-30).
Detected by increased purapout of equipment drain sump.
5)
WR 02/4811 -
RBC weepage at threaded joint to Recirculation 7-11-80 Pumps A & B.
Tightening stopped leak.
f.
Provisions for isolation:
Refer to Figure OP-40-1 (enclosure 2).
For each of the 8 drywell coolers there is an inlet MOV (15-MOV-100A1, A2, A3, A4, B1, B2, 83, 84) and discharge check valves.
Failure of the MOV or a check valve would prevent Individual isolation of the associated cooler, however, manual valves (RBC-23A, B) are provided on the inlet and outlet of each drywell cooling assembly (consisting of 4 drywell
e m n V vi-~v w u
., U.S. Nuclecr R guletory Commission JAFP-81-001
SUBJECT:
NRC ISE BULLETIN 80-24 ENCLOSURE 1 - Pcga 5.
coolers).
Manual isolation of the "A" drywell cooling assembly would also isolate the cooling water supply to the drywell equipment drain sump.
The return from the drywell equipment drain sump cooler is provided with a manual valve (RBC-33).
The supply and return lines to each set of recirculation pump and motor coolers are each provided with a manual Isolation valve (RBC20A, B, and RBC-22A,B). The manual isolation valves are accessible during operation.
The manual isolation of the supply of RBC water to the drywell cooling assemblies and the recirculation pump and motor cooler would not isolate the standby (ESW) source from these components.
A manual valve (ESW-14A, B) is provided to isolate ESW from each recirculation pump and motor cooler. An MOV (15-MOV-103) Isolates ESV from the "B" drywell cooling assembly and another MOV (15-MOV-102) Isolates ESW from both the "A" drywell cooIIng assembly and the drywell equipment drain sump cooler.
Failure of these MOV's in the open position (during ESW operation and supplying loads normally carried by RBC could prevent isolation of the associated components.
These MOV's have provision for manual operation and are accessible during operation.
g.
Isolation Valve Testing:
Testing of isolation valves associated with each containment penetration is conducted at least once each operating cycle as required by 10CFR50 Appendix J and Technical Specification 4.7.A.
Ulth respect to the subject bulletin this testing involves penetrations X-23, 24, and 62 through 68 resulting in test of ESW-15A & B, ESW-16A &
B, RBC-21A & B, 22A & B, 24A & B, 26A & B and 33 These penetrations and valves are shown on enclosure 2.
Summary:
Based on the design characterisitics of the HK-1 containment and drywell sump systems at JAFNPP the probability of significant accumulations, such as those described in the subject bulletin, is very remote. Any source of leakage within the drywell will collect in the sumps. At approximately 1000 gallons, the sumps will overflow to the drywell floor (if no sump pumping capability is available).
Approximately another 10,000 gallons will collect on the drywell floor before overflowing into the Torus.
This approximately 1.2 feet of water on the drywell floor will cause problems no more serious than some wetting of the insulation on the recirculation system pump suction line.
The overflow to the Torus will cause an increase, from normal level, of approximately 1 inch /7000 gallons.
Torus water level is recorded by the operator once each shift and when level exceeds the normal range by 2.5 inches a computer alarm is initiated thus providing assurance that large accumulations of leakage would be detected promptly.
m.
Boyca H. Grier, Dirccter U.S. Nucicer Rsjulctcry Conunission
SUBJECT:
NRC l,E BULLETIN 80-24
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