ML19262A478

Tech Spec Change Request 27 Supporting Licensee Request to Change DPR-90,App A,Re Instrument Channel Check.Certificate of Svc Encl

ML19262A478
Person / Time
Site:	Three Mile Island
Issue date:	12/12/1975
From:	Arnold R METROPOLITAN EDISON CO.
To:
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ML19262A475	List: ML19262A474 ML19262A478
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NUDOCS 7910300419
Download: ML19262A478 (8)

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g METROPOLITAN EDISON COMPANY JERSEY CENTRAL POWER & LIGHT COMPANY AND PENNSYLVANIA ELECTRIC COMPANY THREE MILE ISLAND NUCLEAR STATION UNIT 1 Operating License No. DPR-50 Docket No. 50-289 Technical Specification Change Request No. 27 This Technical Specification Change Request is submitted in support of Licensee's request to change Appendix A to Opers?ing License No. DPR-50 for Three Mile Island Nuclear Station Unit 1. As a part of this request, proposed replacement pages for Appendix A are also included.

METROPOLITAN EDISON COMPANY By i Ih -

Vice PresTdent-Gen'eration Sworn and subscribed to me this / A. day of2ff W ' e , 1975

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POST OFFICE BOX 542 READING. PENNSYLVANI A 19603 TELEPHONE 215 - 929 3601 December 12, 1975 GQL 1798 Mr. Charles P. Hoy, Chairman Board of County Comissioners of Dauphin County P.O. Box 1295 Harrisburg, Pennsylvania 17120

Dear Mr. Hoy:

Enclosed please find one copy of Technical Specification Change Request No. 27 to Appendix A of the Operating License for Three Mile Island Nuclear Station Unit 1.

This request "as filed with the U.S. Nuclear Regulatory Commission on December 12, 1975.

Very truly yours,

/s/ R. C. Arnold R. C. Arnold Vice President RCA:CWS:rk File 20.1.1/7.7.4.3.6.1 1486 290

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POST OFFICE BOX 542 READING, PENNSYLVANI A 19603 TELEPHONE 215 - 929-3601 December 12, 1975 GQL 1798 Mr. Weldon B. Arehart, Chairman Board of Supervisors of Londonderry Township R.D. #1 Geyers Church Road Middletown, Pa. 17057

Dear Mr. Arehart:

Enclosed please find one copy of Technical Specification Change Request No. 27 to Appendix A of the Operating License for Three Mile Island Nuclear Station Unit 1.

This request was filed with the U.S. Nuclear Regulatory Commission on December 12, 1975.

Very truly yours,

/s/ R. C. Arnold R. C. Arnold Vice President RCA:CWS:rk File 20.1.1/7.7.4.3.6.1 1486 291 MeromrQ

THREE MILE ISLAND NUCLEAR STATION, UNIT 1(TMI-1)

Operating License No. DPR-50 Docket No. 50-289 Technical Specification Change Request No. 27 The licensee requests that notes (1) and (2) be added to item #28 of table 4.1-1 of Appendix A of the Technical Specifications by substituting the attached changed pages (4-5 and 4-5a) for page 4-5 of the existing Technical Specifications.

Reasons for the Proposed Change

a. The Appendix A definition of a " check" is :

"1.5.3 INSTRUMENT CHANNEL CHECK An instrument channel check is a /erification of acceptable instrument performance by observation of its behavior and/or state; this verification includes comparison of output and/or state of independent channels measuring the same variable.

The radiation monitor installed check sources are low activity sources.

In spite of all the reasonable cautions taken to minimize monitor background radiation levels, it is possible for the monitor background radiation level to build up to a point (within acceptable radiological parameters) where the additional increment (in cpm) due to the insertion of the check source is quite small in relation to the continuous background radiation level seen by the monitor. Further, when the background reading exceeds twice the value which would result from the check source alone, the background reading is sufficient to meet the requirements of specification 1.5.3(INSTRUMENT CHANNEL CHECK).

b. Area monitors RM-G6, RM-G7, and RM-G8 are located in high radiation areas in the reactor building. These monitors are inaccessible during power operation. The change would merely schedule the quarterly calibrations for the next scheduled reactor shutdown following the quarter in which calibration would normally be due.

Calibration of these monitors during normal operation is contrary to the ALAP philosophy.

Safety Analysis Justifying Tl r Change The probability of occurrence or consequences of an accident or malfunction of equipment important to safety previously evaluated in the Final Safety Analysis Report will not be increased in that:

a. Weekly monitor checks will be performed as required and in a manner that will fulfill the intent of the original speci-fication (i.e. does the monitor respond to radiation properly).

b. RM-G6, RM-G7, and RM-G8 are located in areas where radiation levels are greater than 100 nr/hr (High Radiation Areas) during reactor operation.

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Surveillance of these monitors will be conducted as close to a quarterly basis as possible and still be consistent with ALAP considerations.

Therefore, the intent of the quarterly surveillance (i.e. to ensure monitor reliability) will be fulfilled.

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TABLE 4.1-1 (Continued) r CHANNEL DESCRIPTION CHECK TEST CALIBRATE REMARKS 19 Reactor Building Emergency Cooling and Isolation System Analog Channels

a. Reactor Building S M R h psig Channels

20. Reactor Building Spray NA Q NA System Logic Channel

21. Reactor Building Spray System Analog Channels f a. Reactor Building NA M R

• 30 psig Channels

22. Pressurizer Temperature S NA R Channels 23 Control Rod Absolute Position S(l) NA R (1) Check with Relative Position Indicator

24. Control Rod Relative Position S(l) NA R (1) Check with Absolute Position Indicator 25 Core Flooding Tanks

__, a. Pressure Channels S(l) NA R (1) When Reactor Coolant system pressure 43, is greater than 700 psig CX) b. Level Channels S(l) NA R

26. Pressurizer Level Channels S NA R N

'43 27 Makeup Tank Level Channels D(1) NA h (1) When Makeup and Purification System 42" is in operation

TABLE h.1-1 (Continued)

CHANNEL DESCRIPTION CHECK TEST CALIBRn1B REMARKS

28. Radiation Monitoring Systems W(1) M Q(2) (1) Using the installed check source when background is less than twice the expected increase in cpm which would result from the check source alone.

Background readings greater than this value are sufficient in themselves to show that the monitor is functioning.

(2) Except area gauma radiation monitors RM-G6, RM-GT, and RM-G8 which are located in high radiation areas of the Reactor Building. These monitors will y

be calibrated quarterly or at the next scheduled reactor shutdown following dn

1. the quarter in which calibration would normally be due, if a shutdown during the quarter does not occur.

29 High and Low Pressure Injection NA NA R Systems: Flow Channels CX3 Ch N

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UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION -

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IN THE MATTER OF b -

DOCKET NO. 50-289 OPERATING LICENSE NO. DPR-50 METROPOLITAN EDISON COMPANY This is to certify that a copy of Technical Specification Change Request No. 27 to Appendix A of the Operating License for Three Mile Island Nuclear Station, Unit 1, dated December 12, 1975, and filed with the U. S. Nuclear Regulatory Commission December 12, 1975, has this 12th lay December,1975, been served on the chief executives of Londonderry Township, Dauphin County, Ps'utsylvania, and of Dauphin County, Pennsyl-vania, by deposit in the UniMd States Mail, addressed as follows:

Mr. Weldon B. Arehart, Chairman Mr. Charles P. Hoy, Chairman Board of Supervisors of Board of County Commissioners of Londonderry Township Dauphin County R.D.#1, Geyers Church Road Dauphin County Courthouse Middletown, Pennsylvania 17957 Harrisburg, Pennsylvania 17120 METROPOLITAN EDISON COMPANY t

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Vice President - Generation 13915 1486 296