ML19210B378

Responds to ACRS 730814 Ltr Re Assurance of Provision of Instrumentation for Determining Course of Potentially Serious Accidents at Facility & Availability of Appropriate Calibr Methods.Listing of Instrumentation Encl

ML19210B378
Person / Time
Site:	Three Mile Island
Issue date:	09/10/1973
From:	John Miller METROPOLITAN EDISON CO.
To:	Giambusso A US ATOMIC ENERGY COMMISSION (AEC)
References
NUDOCS 7911070700
Download: ML19210B378 (3)

Text

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. AEC :3U'" ION FOR PART 50 DCCKET m AL (TCiPORARY F0EM) CONTROL NO: 7085 FILE: -

FROM: DATE OF DOC DATE REC'D LTR MEMO RPT OTHER Metropolitan Edison Company Reading Pa. 19603 9-10-73 9-21-73 X J. G. Miller TO: ORIG CC OTHER SENT AEC PDR X A. Giambusso 1 signed SENT LOCAL PDR X CLASS UNCLASS PROP INFO INPUT NO CYS REC'D DOCKET NO:

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DESCRIPTICN: ENCLOSURES:

Ltr re ACRS 8-14-73 ler. . . . . . . . Trans the fol- Post Accident Instrumentation- instrumentation lowing: for determining the course of potentially serious accident ACKNOWLEDGED DO NOT REMOVE PLANT NAME: Three Mile Island Unit-1 ( l cys rec'd )

FOR ACTICN/INFORMATION 9-21-73 GC BUTLER (L) dCBJENCER(L) ZIEMANN(L) REGAN(E)

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W/ Copies W/ Copies W/ Copies W/ Copies COLLER(L) VASSALLO(L) KNIGH' ION (E)

W/ Copies W/ Copies W/ Copies W/ Copies KNIEL(L) ~SCHEMEL(L) YOUNGBLOOD(E)

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METROPOLITAN EDISON COMPANY PCST OFFICE BOX 542 READING PENNSYLVANI A 19603 TE LEPHONE 215 - 929 3601 September 10, 1973 Mr. A. Giambusso 8 Deputy Director for Reactor Projects United States Atomic Energy Comission S 4 Washington, DC 20545 kkC{ggg q

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SUBJECT:

THREE MILE ISLAND NUCLEAR STATION SEP2 UNIT 1 -

U1 a,, 1194 -

DOCKET NO. 50-289 I Com;e75' I

Dear Mr. Giambusso:

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The August 14, 1973 letter written by Mr. H. G. Mangelsdort of the ACRS Comittee to the Honorable Dixy Lee Ray regarding the subject reactor, suggested that the Applicant assure himself that instrumentation for determining the course of potentially serious accidents, on a time scale that will permit approprlate emergency action, is provided at the station. In additior, Applicant was asked to assure that appropriate calibration nethods and calculated bases for interpreting instrument responses are available.

He have reviewed the situation and we are satisfied that:

(1) Adequate instrumentation has been provided; (2) Adequate calibration methods and procedures e.re available; and, (3) Calculated bases for interpreting instrument responses are available.

Enclosed is a listing of the instrumentation available to follow the course of an accident. The list includes references to the appropriate s the FSAR and the Technical Specifi-cations. g/

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g Very truly yours, 1 SEP 21973 . . 2 9 RMUL 1 J. G. Miller

, h[A[k ttgRK Vice President r

Enc.usure uik 1584 317 CC: Mr. W. A. Verrechi

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POST ACCIDENT INSTRUMENTATION .3d ?. '* Lt M

1. Following an accident, the nuclear instrumentation will be available to confirm that the reactor is tripped. (see FSAR Section 7)

2. The balance of the reactor protection system instrumentation located outside of the primary shield will also be available, this in-cludes the measurement of reactor coolant pressure and reactor coolant temperature. (see FSAR Section 7) '

3. The qualification testing of the reactor protection system is discussed in Babcock & Wilcox Topical Report BAW 10003. Rev. 2.

4. We have additional post accident monitoring instrumentation which display, record and alarm in the control room. This instrumen-tation includes the following:

A. The reactor building radiation level, monitored by a high -

range gamma detegtor (channel DI-G8) which has a range of Ir/hr. to 1 X 10 r/hr. (see FSAR Section 11.4)

B. The reactor building pressure with a range of 0-100 PSIG.

(see FSAR Section 7.4.7)

C. The reactor building sump level.

These three measurements are qualified to operate folicwing an accident.

5. There are 12 resistance temperature detectors located in different areas of the reactor building. These resistance temperature detectors are expected to provide information on reactor building temperature after an accident.

6. In addition, we have outside the reactor building the following instruments which indicate in the control room:

A. High Pressure Injection flow (see FSAR Figure 6.2)

B. Low Pressure Injection flow (see FSAR Figure 6.2)

C. Low Pressure Injection pump suction temperature (see FSAR Figure 6.2)

D. Decay heat closed cycle temperature Table 3.5-1 (Instrument Operating Conditions) of Technical Speci-fication 3.5.1 lists the requirements for reactor startup or critical operation. Table 4.1-1 (Instrument Surveillance Requirements) of Tech.

Spec. 4.1 indicates the calibration schedule for the instrumentation mentioned above.

1584 318