ML20137E858

Proposed Tech Spec Changes,Revising RCS Safety/Relief Valve Setpoint & Setpoint Tolerances.No Significant Hazards Consideration Encl

ML20137E858
Person / Time
Site:	LaSalle
Issue date:	08/19/1985
From:	COMMONWEALTH EDISON CO.
To:
Shared Package
ML20137E852	List: ML20137E848 ML20137E858
References
NUDOCS 8508260089
Download: ML20137E858 (4)

Text

r; ATTACINENT B -

PROPOSED CHANGE TO APPENDIX A TECHNICAL -5PECIFICATIONS TO OPERATING LICENSES WF-11 and fPF-18 Revised Pages:

NPF-11 NPF-18 3/4 4-5 3/4 4-6 i

l i

l L 0527K l

I l

8508260089 850819" PDR ADOCK 05000373 P PDR L

u l'

i i.

l L

r REACTOR COOLANT SYSTEM 3/4.4.2 SAFETY / RELIEF VALVES LIMITING CONDITION FOR OPERATION 3.4.2 The safety valve function of eighteen reactor coolant system safety /

relief valves sgall be OPERABLE with the specified code safety valve function,-

lift settings.*

i a. 4 safety / relief valves @ 1205 psig F + 1 7. , ~5 7*

b. 4 safety / relief valves @.1195 psig t +1 9=, - 3 ?-

c. 4 safety / relief valves @ 1185 psig '). , ~ 5 %

d. 4 safety / relief valves @ 1175 psig + 1 7. , - 39,

e. 2 safety / relief valves @ J.Mtf psig +1% -3 %

llSo APPLICABILITY: OPERATIONAL CONDITIONS 1, 2 and 3.

ACTION:

a. With the safety valve function of olie or more of the above required safety / relief valves inoperable, be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTOOWN within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />,

b. With one or more safety / relief valves stuck open, provided that suppression pool average water temperature is less than 110 F, close the stuck open relief valve (s); if unable to close the open valve (s) within 2 minutes or if suppression pool average water temperature is 110 F or greater,_ place the reactor mode switch in the Shutdown position.

c. With one or more safety / relief valve stem posit' ion indicators inoperable, restore the inoperable stem position indicators to l OPERABLE status within 7 days or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

SURVEILLANCE REQUIREMENTS 4.4.2.1 The safety / relief valve stem position indicators of each safety / relief valve shall be demonstrated OPERABLE by performance of a:

a. CHANNEL CHECK at least once per 31 days, and -a

b. CHANNEL CALIBRATION at least once per 18 months.**

4.4.2.2 The low low set function shall be' demonstrated not to interfere with the OPERABILITY of the safety relief valves or the ADS by performance of a CHANNEL CALIBRATION at least once per 18 months.

"The lif t setting pressure shall correspond to ambient conditions of the valves at nominal operating temperatures and pressures.

1. Up to two inoperable valves may be replaced with spare OPERABLE valves with lower setpoints until the next refueling outage.

• • The provisions of Specificatio%4.0.4 are not applicable provided the surveil-(- lance is performed within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after reactor steam pressure is adequate to perform the test.

LA SALLE - UNIT 1 3/4 4-5 Amendment No. 18

REACTOR COOLANT SYSTEM 3/4.4.2 SAFETY / RELIEF VALVES LIMITING CONDITION FOR OPERATION 3.4.2 The safety valve function of 18 reactor coolant system safety / relief valves shall be OPERABLE with the specified code safety valve function lift settings.* #

a. 4 safety / relief valves @ 1205 psigl- + 19. -3 'A

b. 4 safety / relief valves @ 1195 psig tli tl%59.

. c. 4 safety / relief valves @ 1185 psig + +- i s7,', _3 g

d. 4 safety / relief valves @ 1175 psig , + '/., - 3 "7.

e. 2 safety / relief valves @ gpsigJ + n '?.,-3 %

APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, and 3.

ACTION:

a. With the safety valve function of one or more of the above required safety / relief valves inoperable, be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

b. With one or more safety / relief valves stuck open, provided that suppression pool. average water temperature is less than 110*F, close the stuck open relief valve (s); if unable to close the open valve (s) within 2 minutes or.if suppression pool average water temperature is

. 110*F or greater, place the reactor mode switch in the Shutdown j position.

l c. With one or more safety / relief valve stem position indicators inoperable, restore the inoperable stem position indicators to

, OPERABLE status within 7 days or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

SURVEILLANCE REQUIREMENTS 4.4.2.1 The safety / relief valve stem position indicators of each safety / relief valve shall be demonstrated OPERABLE by performance of a:

a. CHANNEL CHECK at least once per 31 days, and a l b. CHANNEL CALIBRATION at least once per 18 months.**

4.4.2.2 The low low set function shall be demonstrated not to interfere with the OPERABILITY of the safety / relief valves or the ADS by performance of a CHANNEL CALIBRATION at least once per 18 months.

• The lift setting pressure shall correspond to ambient conditions of the l

valves at nominal operating temperatures and pressures.

1. Up to two inoperable valves may be replaced with spare OPERABLE valves with l lower setpoints until the next refueling outage.

(-

• • The provisions of Specification 4.0.4 are not applicable provided the surveil-lance is performed within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after reactor steam pressure is adequate to perform the test.

LA SALLE - UNIT 2 3/4 4-6 l

m-ATTAC 6 C Significant Hazards Consideration Commonwealth Edison has' evaluated the proposed Technical

' Specification Amendment and determined that it does not represent a significant hazards consideration. Based on the criteria for defining a significant hazards. consideration established in 10 CFR 50.92, operation of LaSalle County Station Units 1 and 2 in accordance with the proposed amendment will not:

1) Involve a significant increase.in the probability or consequences of an accident previously evaluated because: the overpressure limit as previously analyzed is maintained. The safety valves will be maintained within the allowable limits of the design.

2) Create the possibility of a new or different kind of accident from any accident previously evaluated because:no SRVs are being removed. No new accident is postulated. Full overpressure protection is maintained.

3) Involve a significant reduction in the margin of safety because the

' ability of the SRVs to limit reactor pressure as required will be maintained in accordance with design requirements.

Based on the preceding discussion, it is concluded that the proposed system change clearly falls within all acceptable criteria with respect to ~

the system or component, the consequences of previously evaluated accidents will. not be increased and the margin of safety will not be decreased.

r based on the guidance provided in the Federal Register and the Therefo'e, criteria established in 10 CFR 50.92(e), the proposed change does not

, constitute a significant hazards consideration.

E i

0527K l.

I