ML20012D009

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Proposed Tech Specs Changing Section 4.9.F, LPCI Motor- Operated Valve Independent Power Supplies, on Page 222a
ML20012D009
Person / Time
Site: FitzPatrick Constellation icon.png
Issue date: 03/13/1990
From:
POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To:
Shared Package
ML20012C983 List:
References
NUDOCS 9003260286
Download: ML20012D009 (6)


Text

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ATTACHMENT I j PROPOSED TECHNICAL SPECIFICATION CHANGE REGARDING LPCI MOV INDEPENDENT POWER SUPPLY  :

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(JPTS-85 010) i h

9003260286 900313 A,DR ADOCKOU00g3 $ ,.

7 New York Power Authority i

JAMES A. FITZPATRICK NUCLEAR POWER PLANT Docket No. 50-333 -

DPR 59

JAFNPP .

5.

3.9 (cont'd) 4.9 (cont'd)

' LPCI MOV Independent Power Supplies F. LPCI MOVIndependent Power Supplies F.

1. Every week the specific gravity, voltage and temperature of each pilot cell, and overall battery voltage shall be measured and chargers and inverters shall be visually inspected.
2. Every three months the following measurements shall be made:
a. Voltage of each cell to the nearest of 0.01 v;
b. Specific gravity of each cell;
c. Temperature of every fifth cell.-
3. Once each operating cycle not to exceed 18 months the '

battery shall be subjected to a service test as defined in Reg.

- Guide 1.129 (Batteries).

4. Once each 5-year interval the battery shall be subjected to a -

performance discharge test as defined in Reg. Guide 1.129 (Batteries).

5. Each battery charger and inverter shall be visually inspected weekly and a performance test conducted each operating cycle not to exceed 18 months.
6. Once/ month: open the battery charger A-C input breakers l one at a time and observe performance for proper ope _ ration.

Amendment No. [

222a

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ATTACHMENT ll [

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SAFETY EVALUATION FOR L PROPOSED TECHNICAL SPECIFICATION l CHANGE REGARDING LPCI MOV l lNDEPENDENT POWER SUPPLY ,

l (JPTS-85-010)  :

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l I

New York Power Authority JAMES A. FITZPATRICK NUCLEAR POWER PLANT-Docket No,50-333 DPR-59 l

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Attachment ll

. SAFETY EVALUATION Page 1 of 3  :

l. DESCRIPTION OF THE PROPOSED CHANGE The proposed change to the James A. FitzPatrick Technical Specifications revises Section 4.9.F, -

"LPCI MOV Independent Power Supplies," on page 222a. Surveillance Requirement 4.9.F.6 is

  • revised as follows (affected words underlined):

Replace

  • Once/ month; open the battery charger output breakers one at a time and observe performance for proper operation." ,

with "Once/ month: open the battery charger A-C input breakers one at a time and  !

observe performance for proper operation."

11. PURPOSE OF THE PROPOSED CHANGE The purpose of the Low Pressure Coolant injection (LPCI) Motor Operated Valves (MOV)

Independent Power Supply (IPS) System is to provide an independent power source for the.

operation of three motor operated valves (MOVs) in each of the two redundant LPCI subsystems and for the operation of the two MOVs in each of the two reactor water recirculation pump loops.

The LPCI IPS System is comprised of two separate and independent uninterruptible power supplies each consisting of a battery, an inverter, a rectifier / charger, transformers and associated circuit breakers.

In the event of a LOCA each independent power supply (IPS) is automatically isolated from the Emergency A-C power system. The battery and inverter have sufficient capacity to power the MOV's essential to the operation of the LPCI System. Each IPS is normally fed from the Emergency A C power supply system to maintain the battery in a fully charged state. The output of the IPS provides power to the MOV's.

Surveillance Requirement 4.9.F.6 requires a monthly test of each IPS to verify proper operation of ^

the battery and inverter.- The test is performed by isolating the normal A C power supply (i.e., open circuit breaker 1CB1 on FSAR Figure 8.10-1) and verifying proper frequency and voltage levels.

The proposed change revises Surveillance Requirement 4.9.F.6 to correctly identify the circuit .

breakers used for determining IPS operability. These circuit breakers are on the A-C input side of l the IPS battery chargers (see Reference 3), not the output side as currently indicated .

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  • Attachment 11 SAFETY EVALUATION Page 2 of 3 Ill. IMPACT OF THE PROPOSED CHANGE This change is purely editorialin nature and correctly identifies the circuit breakers used for determining IPS operability. The change does not alter the methodology or frequency of establishing IPS operability as detailed in the surveillance procedures. The change does not impact any paramotor used in an accident analysis and does not place the plant in an unanalyzed -

condition. There is no associated modification to any plant safety structure, system, or component and therefore no impact on the plant's safety margin. Operation of the plant in accordance with this amendment is not a safety concern.

IV. EVALUATION OF SIGNIFICANT HAZARDS CONSIDERATION i Operation of the James A. FitzPatrick Nuclear Power Plant in accordance with this proposed amendment would not involve a significant hazards consideration, as defined in 10 CFR 50.92, ,

since the proposed change would not:  ;

L

1. Involve a significant increase in the probability or consequences of an accident previously evaluated. The proposed change is purely editorial in nature and correctly .

identifies the circuit breakers used for determining IPS operability. The proposed  !

change does not alter the frequency of inspection; nor does it relax any procedures.

The proposed change does not impact nor alter any parameter which is used in determining the likelihood or severity of an accident documented in the FSAR or NRC -

staff's SER. The proposed change does not involve a significant increase in the j probability or consequences of an accident previously evaluated. I

2. create the possibility of a new or different kind of accident from those previously evaluated. The proposed change clearly identifies the circuit breakers used for j determining IPS operability. This change is purely editorial in nature and does not impact operational procedures or maintenance schedules. This change would in no way leave the plant in an unanalyzed condition. The proposed change to the ,

surveillance requirements does not alter any accident analyses nor does it create any  ?

new failure modes. 1

3. involve a significant reduction in the margin of safety. This change is purely editorial in nature and does not relax any administrative controls or limitations. The change  ;

corrects the technical specifications by clearly identifying which circuit breakers are used for meeting the surveillance requirements for the LPCI MOV IPS. This change  ;

does not alter the intent of the surveillance requirement and therefore has no impact on '

the margin of safety.

V. IMPLEMENTATION OF THE PROPOSED CHANGE I t

Implementation of the proposed change will not impact the ALARA Program at FitzPatrick, nor will the change impact the environment, k

Attachment II SAFETY EVALUATION

., Page 3 of 3 i

VI, CONCLUSION This change, as proposed, does not constitute an unreviewed safety question as defined in 10 CFR-50.59. That is,it:

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 l

i

d. Involves no significant hazards consideration, as defined in 10 CFR 50.92. 4 i

Vll. REFERENCES  !

1. James A. FitzPatrick Nuclear Power Plant Updated Final Safety Analysis Report, Section 8.10.
2. i James A. FitzPatrick Nuclear Power Plant Safety Evaluation Report (SER), dated November i 20,1972 and Supplements.
3. NRC letter, R. W. Reid to G. T. Berry, dated September 16,1977 issues Ame7dment 30 authorizing plant operation with independent power supplies for LPCI motor operated valves.

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