ML20069J364

Proposed Changes to Tech Specs Changing Safety Relief Actuating Setpoint of Target Rock Valve to 1,135 Psig & Setpoint of Two Electromatic Relief Valves to 1,115 Psig

ML20069J364
Person / Time
Site:	Quad Cities
Issue date:	10/18/1982
From:	COMMONWEALTH EDISON CO.
To:
Shared Package
ML20069J320	List: ML20069J315 ML20069J364
References
NUDOCS 8210250126
Download: ML20069J364 (3)

Text

. ..

..y x cc .

9 ATT AC HMEN T Quad Cities Station Unit 1 Proposed Changes to Appendix A Technical Specifications to Operating License DPR-29 Revised pages: 1. 2 /2. 2 -l *

-3.6/4.6-4

. ~

• This page includes changes proposed in the T. Rausch letter to H. Denton dated August 19, 1982 (50.59 reloads with ODYN) as supplemented in the T. Rausch to H. Denton letter dated October 18, 1982.

5260N I O J' .-

~

i ~ 82[0250126 821018

PDR ADOCK 05000254 P_ PDR b.

. l i

QUAD-CITir.S

)(40 4f '

DPR- 29 .

i 1.2/2.2 REACTOR COOLANT S'YSTEM  ;

UMIDNG SAFETY SYSTEM SETTINC SAFETY UMIT I APPUcabmty- [

Applicability:

i APPli es to trip settings of the instruments and APPli es to limits on etietor coolant system devices which are provided to prevent the reactor Pressure. sysicm sarety limits from beins esceeded- l t

Objeettss:

.O6jective:

To define the level of the process variables at which [

To establish a limit below which the integrity of the j automatic protective action is initiated to prevent reactor eco! ant system is not thre.itened due to an i the safety limits from being exceeded. ,

overpressure condition. t SPECIFICATIONS i

A. Reactor coolant high. pressure scram shall be

a. n. .u, m ins.,.s ,,.... .. ..., ., u.  !

s1060 pig.

Gr.k.O.*:.:s.,0*:.

to u . . 1  :..". : 'J".il:!: 012,". ',;;;;;'

S. Primary system safety valve nominal settings

- shall be as follows:

1 valve at !!35 psig'" l 2 valves at 1240 psig i 2 valves at 1250 psig l 4 valves at 1260 psig (

l

rfarget Rock combination safety / relief valve j t

The allowable setpoint error for each valve j shallbe i!E )

• i

,- l t

I g&.

~. - I e

I.2/2.21

. . . . . _ . . . ~ . .

pwm + - -

. w a s ,.,.;, w a a .. . .u a ,; _ .

w -

QUAD-CITIES DPR-29 f7&',

P' 2. Both the sump and air sampling sys-tems shall be operable during reactor power operation. From and after the date that one of these systems is made or found to be inoperable for any rea-son, reactor power operation is per-missible only during the succeeding 7 days.

3. If the conditions in I or 2 above cen-not be met, an orderly shutdown shall be initiated and the reactor shall be in a cold shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

E. Safety and Relief Valves E. Safety and Relief Yahes I. Prior to reattor startup for power op- A minimum of I/2 of all safety valves shall be cration, during reactor pow operat- bench checked or replaced with a bench ing conditions, and wh never the reac- checked valve cach refueling outage. The pop-tor coolant pressure is greater than 90 ping point of the safety valves shall be set as psig and ternperature greater than follows:

320' F, all nine of the safety valves shall be operable. The solenoid. Number of Valves Serpoint (psig) activated pressure valves shall be oper-I l135m l able as required by Specification 2 M

, 2 1250

2. If Specification 3.6.E.1 is not met, the 4 1260

. reactor shall remain shut down until the condition is corrected or, if in The allowable setpoint error for each valve is operation, an orderly shutdown shall 1%

be initiated and the reactor coolant pressure and temperature shall be All relief valves shall be checked for set pres-below 90 psig and 320 F within 24 su M refdig my h m pas g,y g hours.

k. ther of Valves Setpoint (psig)

I s 1135

• 2 si115 2 51135

"' Target Rock combination safety / relief valve.

F. Sirm:turalIntegrity F. Structurallategrity The atmetural integrity of the primary system The nondestructive inspections listed in Table bouwry shall be maintained at the level re- 4.61 shall be performed as specified in accor-qhd by the ASME Boiler and Pressure Vessel dance with Section XI of the ASME Boiler and Code,Section XI, " Rules for Inservice Inspection Pressure Vessel Code,1971 Edition, Summer of Nuclear Power Plant Components", 1974 1971 Addends. The results obtained from com-Edition, Summer 1975 Addenda (ASME Code pliana with this specification will be evaluated Section XI). after 5 years and the conclusions will be reviewed

,}, with the NRC.

3.6/4,6-4 Amendment 33

~