ML19324B736
| ML19324B736 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 10/27/1989 |
| From: | DUKE POWER CO. |
| To: | |
| Shared Package | |
| ML19324B734 | List: |
| References | |
| NUDOCS 8911080111 | |
| Download: ML19324B736 (6) | |
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. CONTAINMENT SYSTEMS CONTAINRENT VALVE INJECTION WATER SYSTEM b
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F 3.6.6 Both trains of the Containment Valve Injecticn Water System shall be
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APPLICABILITY:
MODES 1, 2, 3 and 4.
ACTION:
'With one train of the Containment Valve Injection Water System inoperable, restore the irocerable system to OPERABLE status within 7 days or be in'at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTOOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
j SURVEILLANCE REQUIREMENTS EachtrainoftheContainmentValveInjectionWaterSystemst[allb NW5 4.6.6.1 t
demonstrated OPERABLE at least once per 31 days by verifying that thetg.tc.
is pressurized to greater than or equal to M ^ ", O~,.^ y..y nd has ade-quate capacity to maintain system pressure for at least 30 days.
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4.6.6.2 Each train of the Containment Valve Injection Water System shall be demonstrated OPERABLE at least once per 18 months by verifying that the vehe
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l CATAWBA - UNITS 1 & 2 3/4 6-54 Amenoment No.
(Unit 1)
Amendment No.
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a U-DISCUSSION AND JUST1FICAT10N OF NO SIGNIFICANT HA2.ARDS CONSIDERATION The proposed amendment would eliminate en inconsistency between the Containment Valve Injection Water (NW) System Surge Tank lo-lo pressure
.setpoint and valve seal injection flow rate specified in Surveillance t
Requirements 4.6.6.1 and 4.6.6.2 and the more conservative limits required by Duke Power design analyses. Tho more conservative limits are teing administrative 1y implemented at Catawba Nuclear Station at the pre.sent time.
t The purpose of the NW System is to inject water between the two seating surfaces of double disk flex wedge gate valves at a pressure higher than containment design pressure. The injection of a pressurized fluid p: events leakage past these valves and reduces potential off-site doses following a Loss of Coolant Accident. The NW system consists of two independent redundant trains per unit.
Each train includes a surge chamber filled with water and pressurized with nitrogen. One main header exits the chamber and splits into several branch headers. Makeup water is provided from the Domineralized Water Storage Tank for testing and chamber makeup during normal operation. Assured makeup is provided from the Nuclear Service Water System. Water'is injected automatically on an Engineered Safety System signal. The NW System is described in FSAR Section 6.2.4.2.2 and shown in FSAR figure 6.2.4-2.
The Containment Isolation valves served by the NW system and portions of the NW system itself are tested simultaneously. Testing is accomplished by performing leakage tests on groups of valves. Valves are grouped by relative location.- The leak rates are summed for all of the group tests.
This total value is compared to the system allowable leakage to determine system compliance with its design basis. Containment isolation valves are leak rate tested by injecting seal water from the NW system to the isolation valves. With the containment isolation valve closed, the leakage is determined by measuring flow rate of seal water out of the NW systen Surge Tank. The total leakage from each train is not to exceed the Technical Specification limits. Testing and inspection of containment isolation valves is discussed in FSAR Section 6.2.4.4.
Design calculations to determine the current Technical Specification Surveillance Requirements 4.6.6.1 and 4.6.6.2 for Surge Tank pressure and I:
allowable NW System leak rates assumed a two pump Nuclear Service Water System configuration. The Catawba Nuclear Service Water System has been reanalyzed in a one pump configuration. Therefore, the Technica]
l Specification Surge Tank pressure allowable leak rate calculations do not J.
account for the revised Nuclear Service Water System header pressure.
Additionally, the original design calculation to determine the Technical Specification 4.6.6.1 NW System Surge Tank low low pressure setpoint did not properly account for the dynamic head loss.
L The proposed change to Surveillance Requirement 4.6.6.1 is necessary to accurately reflect the current setup of the NW System. The only portion of the NW System which is filled and pressurized is the surge tank. The NW System is isolated downstream of the surge tank such that the entire NW System is not pressurized, as this surveillance would indicate. The l
proposed 36.4 psig NW Surge Tank pressure requirement is more conservative that the current 16.2 psig pressure requirement. The higher NW Surge Tank pressure requirement reflects the revised design calculations of the Nuclear Service Water System and the Contaitunent Valve Injection Water System. The proposed 36.4 psig NW Surge Tank pressure also accounts for the dynamic head loss. The proposed change will not make this burveillance l
any less restrictive.
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The proposed change to' Surveillance Requirement 4.6.6.2 removes allowable leakage values from the Technical Specifications. Test Acceptance Criteria
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. Data Sheets have been.lssued to provide the station with the proper l
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. surveillance test requirth?nts.. Duke Power has imposed lower allowable i
sleakage values than required by Technical Specification 4.6.6.2 to ensure
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the W system meeta-the design basia... Duke Power has performed and x
. documented an operability evaluation. This evaluation demonstrates that-by p
observing the administrative leakage limits, the W system will maintain a b
pressure of 1.1 Pa at.the furthermost gate valve served by the system.
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. Revised Nuclear Service Water System analysis, dynamic flow losses, and i.
lo-lo W Surge Tank pressure have been considered in the development of new
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allowable. leakage limits.. This analysis coacluded that the W system, as currently designed and installed, meets its design function provided that o
syrtem leakage does not exceed maximum previous performance test leakage values. - Since the proposed W system leakage limits are more conservative j',
than those required by Surveillance Requirement 4.6.6.2, a change to the i
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Technical Specifications is warranted. The proposed furveillance
,; W Requirement would reestablish consistency between the design calculations
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and the Technical Specification.
The proposed deletion of the Technical Specification page 3/4 6-54 footnote is an administtative change which does not impact any Technical Specification. The footnote only pertained to the catawba Unit 2 refueling outage 1 and is no longer applicable to any Technic.r.1 Specification.
Surveillance Requirement'4.6.6.2 is not any less restrictive as a result of-
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L 10 CFF 50.92 states that a proposed' amendment involves no significant
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hazards consideration.if operation in accordance with the proposed
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amendment would nots (1) Involve a significant increase in the probability or consequences of an accident previously evaluated; or F
(2) Create the possibility of a new or different kind of accident
-from an accident previously evaluated; or (3) Involve a significant reduction in a margin of safety.
The proposed amendment does.not involve an increase in the. probability or consequence of any previously evaluated accident. The proposed Surveillance Requirements 4.6.6.1 and 4.6.6.2 allowable W Surge Tank pressure and leak rates have no offect on the initiation of any accident postulated in the FSAR. The more conservative Surveillance Requirements ensure proper injection flow to valves serviced by the W system. The W l
system will continue to perform its intended safety function and meet its i
design basis. Therefore, the proposed amendment does not involve an increase in the probability of an accident previously evaluated. The i
j; postulated change does not involve an increase in potential off-site doses G
'following a Loss of Coolant Accident. Therefore, the proposed amendment u
does not involve an increase in the consequence of aay previously evaluated p'
accident.
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hheproposedamendmentdoesnot'createthepossibilityofanewor different kind of-accident from any accident previously evaluated. Duke Poker analyses demonstrate that the proposed amendment ensures the NW system meets the design basis of 1.1 Pa injection pre-sure of the furthermost valve serviced by the system. The~ proposed change does not' introduce unanalyzed conditions or modes of operation, and the operability.of the NW system is preserved. Therefore, the proposed amendment does not create the possibility of a new or different kind of accident from any accident previously evaluated.
The proposed changes to Surveillance Requirements 4.6.6.1 and 4.6.6.2 do not involve any~ reduction in a' margin of safety. The proposed limits on NW system Leakage ensure that injection water is delivered to the containment isolation valves following the postulated LOCA at a pressure sufficient to ensure that !?W system design basis is met. Duke Power analysis of allowabic NW 1eakage limits account for the lowest NW surge chamber t.
pressure and for dynamic flow losses to the furthermost gate valve while still demonstrating 1.1 Pa injection pressure at that valve. Thus, the L
margin of safety is preserved.
The proposed deletion of the Technical Specification page 3/4 6-54 is an administrative change which does not involve any unreviewed safety consideration.
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For the above reasons, it is concluded that this proposed license amendment does not involve significant hazards considerations.
Environmental Impact The proposed Technical Specification change has been reviewed against the criteria of 10'CFR 51.22 for the environmental considerations.
As shown above, the proposed change does not involve a significant hazards consideration, nor increase the types and amounts of effluents that may be released offsite, nor increase individual or cumulative occupational radiation exposures. Based on this, the proposed Technical Specification change meets the criteria given in 10 CFR 31.22(c)(9) for a categorical exclusion from the requirement for an Environmental Impact Statement.
For all the above reasons, Duke Power concludes that this proposed amendment does not involve any Significant Hazards Considerations.
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