ML20235E109

From kanterella
Jump to navigation Jump to search
Requests Addl Info,Including Turbine First Stage Pressure Bypass Setpoint Corresponding to 45% Rated Steam Flow,Calibr of Ionization Chambers to Complete Changes to Be Made to Tech Specs for 100% Rated Power License by 720830
ML20235E109
Person / Time
Site: Quad Cities, 05000000
Issue date: 07/26/1972
From: Skovholt D
US ATOMIC ENERGY COMMISSION (AEC)
To: Brian Lee
COMMONWEALTH EDISON CO.
Shared Package
ML20235B311 List: ... further results
References
FOIA-87-111 NUDOCS 8709250484
Download: ML20235E109 (3)


Text

- _ _ _ _ _ _ - _ _ _____

JUL 2 61972 Docket Nos. 50-254 and $0-265 a

Commonseelth Edison Company ATTN 4 Ar. Byron Lee, Jr.

Assistant to the President Post Office Box 767 Chicago, Illicois 60690 Gentlemen.

..uring recent meetings with representatives of your Company, required changsc in the Quad-Cities ' Units 1 and 2. Technical Specifications (TS) were developed and discussed.

A number of these changes will be made prior to our issuance of a license for continuous operation at 90%

of rated power with the diffuser-pipe operational as requested by your letter dated July 7, 1972. Additional changes to the TS developed and discussed in the meetings will be rsquired prior to our issuance of an operating license for 1001 of rated power.

To complete the chengas to be made to the TS for the 100% rated power license, tne following additional information or changes are required:

1.

Turbine first stage pressure bypass set point corresponding to 45% rated steam flow is required. We were advised that

' this has been, or will be, established during startup tests.

2.

Ionization chambers presently are installed as sensors for isolation from high radiation in the main steam lines and staan jet air ejsctor off-gas lines. Such sensors should be calibrated quarterly. Check sources may be substituted for calibration of sensors not accessible during reactor operation, in which casa complete calibration would be required during each refueling outage.

3.

Control rod position indication surveillance specifications and bases need to be established.

4.

Additional specifications (limiting conditions of operation and surveillance with bases) are needed for the Rod Worth Minimiser (RWM). Operation of the RWM is required when the reactor is in the Startup/ Hot' Shutdown mode.

b ',.

8709250484 870921 PDR -FOIA MENZ87-111 PDR

-_1-____-__

^

i l

?.

1 Commonwealth Edison Company g gg g i

5.

References to Dresden 2/3 FSAR amenenents in TS shall be replaced with the appropriate Quad-Cities FSAR amendments even if these amen &nents further reference the Dresden amendnents.

6.

You have proposed that the control rod serem surveillance frequency should be changed. Provide justification for j

the proposed change.

]

7.

The TS for the system that maintains full discharge pipes in the ECCS require additions to adequately address the safety aspects-of the filling system with respect to the ECCS.

J l

8.

A TS requiring verification of operable jet pumps af ter a l

reactor coolaat recirculation pump has tripped is required.

9.

Specifications for surveillance of isolation capability of the feedwater system check valves are required.

10.

The limiting condition of operation (LCO) and surveillance I

with bases for the pressure suppression chamber vacuum breakers

)

to the dryvell are not adequate. Prarsure tests, acceptable off-seat position prior to a 14CA, and frequency of operability tests and instrument checks should be included.

11.

You indicated that you presently are reviewing control rod

)

and control rod drive maintenance specifications in con-sideration of proposing some changes,.ppropriate justifi-

'j cation must be provided for any proposed changes.

12.

The administrative sect.on of the TS is to be revised te be similar to that of Zien.

13. A change in the reactor pressure set point for bypassing scram from main steam line isolation valve closure and main condenser low vacuum when the reactor mode switch is in the Startup/ Hot Standby position was made prior to initial licensing on October 1, 1971. The set point was changed from 600 psi to 1060 pai reactor pressure. We have no justifi-cation in our records for this change. You presently propose to remove the bypass set point of 1060 psi from the TS because it is redundant to the high pressure scram. Jus tification for the change of the set point from 600 psi, as now stated i

i.

Commonwealth Edison Company y g.g jgp in the FSAR, must be provided. Also advise if the bypass switches have been removed from the reactor protectiva system circuits. If they have not been removed, advise

. what monitoring and tests will be included in the TS to verify that the switches have not failed in an unsafe manner.

The above information should be submitted as proposed changes to the TS with appropriate amendment of the FSAR.

Your response to the items listed above is required on or before August 30, 1972, to provide sufficient time for evaluation prior to licensing of Units 1 and 2 for operation at 1001 rated power.

Sincerely, NA Donald J. Skovholt Assistant Director for Operating Reactors Directorate of Licensing cct Mr. Charles Whitmore Distribution Frosident and Chairman Iowa-1111acis Gas and WDooly, DR Electric Company R0 (3) 206 East Second Avenus HShapar, OGC Davenport, Iowa 52801 JRBuchanan, ORNL PDR Incal PDR John W. Rowe, Esquire

&&6cket Files Isham, Lincoln & Beale Counselors at Law DL Reading One First National Plasa Branch Reading ACRS (16)

Chicago, Illinois 60670 ASLBP MRowden, OGC MKarman, OGC IUSkovholt, DL TJCarter, DL DLZiemann, DL JIRiesland, DL RMDiggs, DL I

omer*.L!.9.RB,J2

,,,,L LLORB #2 L:0R Jn W

..,48, 8,n,4 jjj.I).....

,, p,,,,,, DLZiemann Olt

,l 8

SURNAug >

DATt >.2/.2.5/,72,,

,,7/25/72 7/D[72, 7/ (),/,7,2 Forns ABC-Sit (Rev. 9-$3) ASCM ONO e.o ess-to-suu-s uHfs l

4

.