ML20076M712

Proposed Tech Spec Pages 1.2/2.2-1 & 3.6/4.6-4 Re Rcs. Evaluation of Significant Hazards Consideration Encl

ML20076M712
Person / Time
Site:	Quad Cities
Issue date:	07/15/1983
From:	COMMONWEALTH EDISON CO.
To:
Shared Package
ML20076M705	List: ML20076M701 ML20076M712
References
6951N, NUDOCS 8307210052
Download: ML20076M712 (4)

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Proposed-Changes to Appendix A .

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TechniEal Specifications tof0per'ating; License DPR-30 .-

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• QUAD-CITIES

,- . DPR-30 sf 1.2/2.1 REACTOR COOLANT SYSTEM SAFETY LIMIT LIMITING SAFETY SYSTEM SETTING Applicability: Appiicability:

Applies to limits en reactor coolant system Applies to . trip settings of the instruments and pressure. devices which are provided to prevent the reactor system safety limits from being exceeded.

Objective: Objectiv'e:

To establish a limit below which the integrity of the To define the level of the process variables at which reactor coolant system is not threatened due to an automatic protective action is initiated to prevent overpressure condition. the safety limits from being exceeded.

SPECIFICATIONS A. Se nector ocelant system pressure as asesured A. Reactor coolant high. pressure scram shall be w the vessel steam space ymesure ladionier aball not exceed 1345 pois at say time e en S1060 P53'8-1rrediated mael is pneent la the reactor vessel.

B. Primary system safety valve nominal settings shall be as follows:

1 valve at 1135 psig l 2 valves at 1240 peig 2 valves at 1250 psig 4 valves at 1260 psig terrarget Rock combination safety / relief valve The allowable setpoint error for each valve shall be i15 l

l 1.2 /2.2-1 AMENGIENT No. 51, 69

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j Ql1AD-CITIES DPR-30 q

2. Both the sump and air sampling sys- l arms shall be operable during reactor

• power operation. From and aner the ,

date that one of these systems is made or found to be inoperable for any ses-son. reactor power operation is per-snissible only during the secoseding 7 6p.

3. If the conditions in I or 2 above can-not be met, an orderly shutdown shall be initiated and the reactor shall be in .

a cold shutdown condition within 24 n hours. --

E. Safer) and Relief Yalves E. Safety and Relier Valves I. Prior to reactor startup for power op- A minimum of 1/2 of all safety valves shall be eration, during reactor power operat- bench checked or replaced with a bench ing conditions, and whenever the reac. checked valve each refueling outage. The pop-not coolant pressure is greater than 90 ping point of the safety valves shall be set as psig and temperature greater than follows:

320' F, all riine of the safety valves .

shall be operable. The solenoid- Number of Yahes Serpoint (psig) activated pressure valves shall be oper.

sble as required by Specincation 1 Il35'u l 3.5.D. 2 12 4 2 1250

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

. reactor shall remain shut down until the condition is corrected or, if in The allowable seapoint error for each valve is operation. an orderly shutdown shall *IE be initia:ed and the reae:or coolant

. pressure and temperature shall be M 2rwh M1 k Md fu m p below 90 psig and 320 F within 24 sure each refueling outage. The set pressures hours.

gjg Number of Yahes Setpoint (psig)

I s i135'u 2 s1815 2 51135 "rTarget Rock corabination safery/ relief valve.

F. StructuralIntspity F. Structuralisteytty The structural htegrity of the, primary sysem The mondestructive bspections listed h Table boundary sha!! be maintained at the level re- d.6-1 shad be performed u specifad b accor.

quired by the ASME Soiler and Ptessure Vessel dance with Section XI of the ASME SoGer and Code,Section XI, " Rules for Inservice Inspection pressure Vessel Code,1971 Edition, Summer  ;

of Nuclear Power plant Components".1974 1971 Addenda. The results obtained from erm-Edition, 3mnmer 1975 Addenda (ASME Code pliance with this specification wit! be evaluated Section XI). after 5 years and the socclusions wfIl be reviewed with the NRC.

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3.6/4,6-d Amendment No. 51 -

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ATTACHMENT 2 EVALUATION OF SIGNIFICANT HAZARDS CONSIDERATION Our review of the proposed amendment finds it, when measured against the standards of 10 CFR 50.92, involve no significant hazards consideration. Under 50.92 this means that the proposed amendment does not: (1) Involve a significant increase in the probability or consequences of an accident previously evaluated; or (2) create the possibility of a new or different kind of accident from any accident previously evaluated; or (3) involve a significant reduction in the margin of safety.

The Commission itself has provided further guidance concerning the application of these standards by providing certain examples (48 FR 14871) from which no significant hazards consideration can be made. One

'such example, although related to reload amendments, is clearly applicable here. That example allows for o determination of no significant hazards consideration where no significant changes are made to the criteria of the technical specifications, the analytical methods used to demonstrate conformance with the technical specifications and regulations are not significantl acceptable. y changed and that The required the NRC licensing has previously analyses found such for the upcoming methods Cycle 7, using analytical methods previously approved by the Commission, were performed with the proposed relief valve setpoints. The results of these analyses were found to comply fully with and to be conservatively bounded by the current provisions of its licenses and appendices with no significant affect on any safety margin.

Furthermore, based on a finding by the NRC of no significant hazards consideration for a similiar amendment made on a sister unit at the same facility (Quad Cities Station Unit 1 - Amendment 83 to DPR-29, i dated December 12, 1982) we believe that a precedence exists for a 1 identical conclusion in this case.

Therefore, when reviewed against the criteria of 10 CFR 50.92, reviewed against a specific example provided by the Commission and when reviewed against a similar request for an identical unit at the same i facility we propose a. determination of-no significant hazards considera-

, tion be made.

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