ML20247H821
| ML20247H821 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 05/19/1989 |
| From: | POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK |
| To: | |
| Shared Package | |
| ML20247H775 | List: |
| References | |
| JPTS-89-001, JPTS-89-1, NUDOCS 8905310338 | |
| Download: ML20247H821 (11) | |
Text
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ATTACHMENT I L30 POSED TECHNICAL SPE_QIFICATION CHANGES REGARDING FIRE PUMPS ACTUATION SETPOINTS 1 <
(JPTS-89-001) l I
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I JAMES A. FITZPATRICK NUCLEAR POWER PLANT l Docket No. 50-333 J DPR-59 l l 1
" 8905310338 PDR 890519
.P ADOCK 05000333 PDC .
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ATTACHMENT II j i '
7%FETY EVALUATION _ FOE PROPOSE 0 TECHNICAL SPECIFICATION i CHANGEC REGARDING FIRE PUMPS ACTUATION SETPOINTS LJPTS-89-001)~
l i
New York Power Authority JAMES A. FITZPATRICK NUCLEAR POWER PLANT Docket No. 50-333 'I DPR-59 I,
i C______.________. _ _ _ _ _ _ . _ . _ _ _ _ _ . _ .
Attachment II.
SAFETY EVALUATION Page 1 of 5 I. DESCRIPTION'OF THE PROPOSED CHANGES The proposed changes to the James A. FitzPatrick Technical i
~ Specifications revise surveillance requirement 4.12.A.1.e.4, L Bases 3.12 and 4.12 and Tables 3.12.1 and-4.12.1 on pages 244b, 244h, 244j-and 244g.
- 1. Surveillance requirement 4.12.A.1.e.4; "Nich Pressure Water Fire Protection System" on Dace 244b 1
Replace the phrase, "(at 95 psig for the electric pump and 85 psig for the diesel driven pump)," with "(at greater than or equal to 105 psig for the electric pump and greater than or equal to 95 psig for the diesel driven pump)."
- 2. Bases 3.12 and 4.12 " Fire Protection Systems" on Da.ge 244h
- n. Replace the following sentences from the first paragraph of item A.
"The high pressure water fire protection header is normally maintained at 100 psig by a pressure maintenance subsystem. When pressure decreases to 95 psig the electric motor driven pump is automatically started by its initiation logic. When the higP pressure water fire protection decreases to 85 psig the diesel driven pump is automatically started by its initiation logic."
with "The high pressure water fire protection header is normally maintained at greater than 115 psig by a pressure maintenance subsystem. If the pressure decreases, the fire pumps are automatically started by their initiation logic to maintain the fire protection system header pressure."
- b. Add the following paragraph after the first paragraph of Basis 3/4.12.A:
"A third fire pump, diesel driven, has been installed and is set to actuate upon decreasing pressure after the actuation of the first two pumps. No credit is taken for this pump in any analyses and the requirements of Technical Specifications 3.12 a'nd 4.12 do not apply."
- 3. Table 3 t12.1 " Water Sprav/ Sprinkler Protected Areas" on page 244i Replace the description in the " AREA" column for item 8,
" Diesel Fire Pump Room," with " West Diesel Fire Pump Room."
m_.m -
.-____m.m__ _ - - - - . - - _ _ - . . . - . - - -.
Attachment II SAFETY EVALUATION Page 2 of 5
- 4. Tabic 4.12.1 " Water Sprav/SD_rinkler System Tests" on pace 244c Replace the description in the " AREA" column for item 8,
" Diesel Fire Pump Room," with " West Diesel Fire Pump Room."
II. PURPOSE OF THE PROPOSED CHANGE 8 In order to meet the requirements of the New York Uniform Fire Prevention and Building Code for the newly constructed Training Center - North Region (TCNR) Facility, a new site utility fire protection yard loop was installed to provide fire protection water to the TCNR facility sprinkler systems and hose stations.
The new site utility yard loop is connected to the existing fire protection loop by two cross connections. Each cross connection has a normally open isolation valve.
The source of water for the Fire Protection System is Lake Ontario water which reaches the plant through the screenwell.
The water is supplied to the distribution system by either an electric motor driven pump or diesel driven pump, the latter of which is used for standby and emergency use on the loss of electric power. Each pump is rated at 2500 gpm at 125 psig and can supply 100% of the water requirements of the Fire Protection System. Hydraulic calculations have been performed and it has been determined that each of the existing fire protection pumps can sufficiently provide the required flow to the existing fire protection loop and the new site utility yard loop. In the unlikely event of a pipe rupture in the new site utility loop no degradation of the Fire Protection Water Supply System will take place. The loss in pressure will activate the first fire protection pump; operations will be alerted and will proceed to isolate the leak.
The entire new site utility yard loop is classified as a QA Category III system, with QA Program Category "M" applied to the connections to the existing plant fire protection loop. The entire installation was designed and furnished in accordance with the requirements set forth in NFPA-13, 20, 24 and ANSI B31.1 (1967) through 1969 Addenda. The underground fire protection piping is installed below the established freeze line. The minimum ground cover above the top of the fire protection yard piping is 6 feet.
Though the Fire Protection system including the new site utility loop meets the design basis requirements as wall as commitments to BTP 9.5-1, a second 100% capacity diesel driven pump, driver and accessories have been installed. The new equipment is enclosed in a 3 hour3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> fire rated room located in the Screenwell Building at elevation 255. A sprinkler system, hose station and smoke detectors have been added to protect this new equipment.
1 A_____ _ _
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Attachec ; II SAFETY 'iLUATION Pagc 3 of 5 The new diesel driven fire pump, driver and accessories are designated QA Program Category "M" with Class II seismic loading criteria applied and evaluated as a design load condition.
This applies to the new fire pump, fire pump supports, piping supports, new diesel driven fire pump enclosure, ventilation duct supports and-sprinkler supports. The electrical conduit routed through safety related arecs is seismically supported. This ensures the new fire pump installation will not impact adjacent safety related equipment or structures.
The installation of the new diesel driven pump does not impact the design basis requirements nor does it affect the commitments to BTP 9.5-1. It was considered prudent to install the new diesel driven pump due to the substantial addition of the site utility yard loop to the existing fire protection system. As the use of the new pump is considered for nonnuclear facilities and buildings and no credit is taken for its use in providing fire protection water to any safety related areas, it ic not subject to the requirements of the technical specifications. The setpoint of the new diesel driven pump was set at 85 psig. To minimize "deadheading" the system by starting two pumps at.the same time, the setpoints for the two existing fire pumps were changed. The setpoint for the electric motor driven pump has been changed from 95 psig to greater than or equal to 105 psig and the setpoint for the existing diesel driven pump has been changed from 85 peig to greater or equal to 95 psig.
Changes [1] and [2] above revise the surveillance requirements and basis for the automatic initiation logic of the existing fire protection pumps. These proposed changes allow the setpoints of the existing fire protection pumps to be changed to reflect the installation of the new diesel driven fire pump.
Changes [3] and [4] revise Tables 3.12.1 and 4.12.1 to reflect the addition of a second diesel fire pump room.
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III. IMPACT OF THE PROPOSED CHANGES ;
The installation of the new site utility yard loop requires an update to the FSAR description of the Fire Protection System and FSAR Figure 9.8-1. The installation of the site utility yard loop does not change the assumptions used in the FSAR or any other safety analysis reports. Hydraulic calculations were performed to determine the available pressure in the system.
These calculations concluded the existing fire pumps can sufficiently provide the required flow to both the existing fire protection loop and the new site utility yard loop.
l l The actual installation of the new diesel driven pump, driver and l accessories has no impact on safety. The new diesel driven fire pump, driver and accessories are designated QA Program Category
1
- I Attachment II BAFETY EVALUATION Page 4 of 5 i
"M" with Class II seismic loading criteria applied and. evaluated I as a design load condition. This applies to the new fire pump, l
fire pump cupports, piping supports, new diesel driven fire pump l enclosure, ventilation duct supports and sprinkler supports. i All electrical conduit routed through safety related areas are ,
seismically supported. This was done to ensure the new fire l pump installation will have no impact on adjacent safety related equipment or structures. New piping installed inside the ]
Screenwell Building has been reviewed and it was found not to '
impact any safety-related equipment.
An analysis wan performed to verify the structural adequacy of the existing screenwell structure with the installation of the new diesel driven fire pump, piping and enclosure. It was l determined the existing structure is adequate to support all i loads ~ imparted by this installation under the governing load condition.
The only impact the installation of the new diesel driven pump is to the Technical Specifications. The setpoints of the two existing pumps have been revised and the existing diesel fire pump room has been renamed the west diesel fire pump room.
IV. EVALUATION _OF SIGNIFICANT HAZARDS CONSIDERATION Operation of the James A. FitzPatrick Nuclear Power Plant in accordance with the proposed amendment would not involve a significant hazards consideration as defined in 10 CFR 50.92, since it would not:
- 1. involve a significant increase in the probability or consequences of an accident previously evaluated. The installation of the site utility yard loop and the new diesel driven fire pump, its driver and accessories and the revision of the existing pump setpoints do not affect the assumptions used in the FSAR or any other safety analysis reports. The revision of the existing pump )
setpoints makes the operation of the fire protection system more conservative as the pumps will be started i sooner. These changes have no impact on plant safety operations. The changes will have no impact on previously evaluated accidents.
- 2. create the possibility of a new or different kind of accident from those previously evaluated. The proposed amendment involves the changing of the existing pump setpoints to a more conservative value. These changes cannot create the possibility of a new or different kind of accident.
- 3. involve a significant reduction in the margin of safety.
l Attcchm nt II
! BAFETY EVALUATION Page 5 of 5 The installation of the new site utility yard loop and the diesel driven pump including its driver and accessories do not cause any reduction in safety margins nor do they affect any plant safety system. The changing of the existing fire pump setpoints increases the margin of safety for the Fire Protection System by starting the fire pumps sooner.
V. IMPLEMENTATION OF THE PROPOSED CHANGE Implementation of the proposed changes will not impact the ALARA or Fire Protection Programs at FitzPatrick, nor will the changes impact the environment.
VI. CONCLUSION The changes, as proposed, do not constitute an unreviewed safety question as defined in 10 CFR 50.59. That is, they:
- a. will not increase the probability of occurrence or the consequences of an accident or malfunction of equipment important to safety previously evaluated in the safety analysis report;
- b. will not increase the possibility for an accident or malfunction of a different type than any evaluated previously in the safety analysis report;
- c. will not reduce the margin of safety as defined in the basis for any technical specification; and
- d. involves no significant hazards consideration, as defined in 10 CFR 50.92.
VII. REFERENCES
- 1. James A. FitzPatrick Nuclear Power Plant Updated Final Safety Analysis Report, Section 9.8.
- 2. James A. FitzPatrick Nuclear Power Plant Safety Evaluation Report, dated November 20, 1972 and Supplements.
- 3. James A. FitzPatrick Nuclear Power Plant Fire Hazard Analysis, dated April 1977, Revised November 1983.
- 4. James A. FitzPatrick Nuclear Power Plant Safety Evaluation Report, dated August 1, 1979.