ML19210B102
| ML19210B102 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 03/03/1977 |
| From: | Reid R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19210B100 | List: |
| References | |
| NUDOCS 7911040043 | |
| Download: ML19210B102 (6) | |
Text
[pa #8cqb, NUCLEAR REGULATORY COMMISSION UNITED STATES 3"
W ASHINGTON. D. C. 20555 f
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METROPOLITAN EDISON COMPANY JiRSEY CENTRAL POWER AND LIGHT COMPANY PENNSYLVANIA ELECTRIC COMPANY DOCKET NO. 50-289 THREE MILE ISLAND NUCLEAR STATION, UNIT NO.1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 24 License No. DPR-50 The Nuclear Regulatory Commission (the Commission) has found 1.
that:
The application for amendment by Metropolitan Edison A.
Company, Jersey Central Power & Light Company and Pennsylvania Electric Company, (the licensees) dated 12, 1975, complies with the standards and December requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; The facility will operate in conformity with the B.
application, the provisions of the Act, and the rules and regulations of the Comission; There is reasonable assurance (i) that the activities C.
authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; The issuance of this amendment will not be inimical to D.
the common defense and security or to the health and safety of the public; and The issuance of this amendment is in accordance with 10 CFR E.
Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
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Accordingly, the license is amended by changes to the Technical 2.
Specifications as indicated in the attachment to this license amendment, and paragraph 2.c.(2) of Facility Operating License No. DPR-50 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 24, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
This license amendment is effective as of the date of its 3.
issuance.
FOR THE NUCLEAR REGULATORY COMMISSION 4sh ];$.
^M Robert W. Reid, Chief Operating Reactors Branch #4 Division of Operating Reactors Attachment.
Changes to the Technical Specifications Date of Issuance: March 3, 1977 n,g
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ATTACHMENT TO LICENSE AMENDMENT NO. 24 FACILITY OPERATING LICENSE NO. DPR-50 DOCKET NO. 50-289 Remove pages 4-5 and 4-6 from the Appendix A Technical Specifications and insert the attached pages 4-5, 4-5a and 4-6.
The changed areas On the revised pages are shown by marginal lines.
Page 4-6 is unchanged and is included for convenience only.
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TABIE h.1-1 (Continued) c=
!.l CHANNEL DESCRIPTION CHECK TEST CALIBRATE REMARKS e
3 19 Reactor Building Emergency z
Cooling and Isolation
)
System Analog Channels s
a.
Reactor Building S
M R
h psig Channels 9
20.
Reactor Building Spray NA Q
NA System Logic Channel 21.
Reactor Building Spray System Analog Channels a.
Reactor Building NA M
R 30 psig Channels w
22.
Pressurizer Temperature S
NA R
Channels 23 Control Rod Absolute Position S(1)
NA R
(1) Check with Relative Position Indicator 2h. Control Rod Relative Position S(l)
NA R
(1) Check with Absolute Position Indicatorg 25 Core Flooding Tanks a.
Pressure Channels S(l)
NA R
(1) When Reactor Coolant system pressur,e is greater than 700 psig b.
Ievel Channels S(1)
NA R
- 26. Pressurizer Level Channels S
C4 R
C/;
27 Makeup Tank Level Channels D(1)
NA R
(1) When Makeup and Purification System Ln is in operation CO DO k
TABLE h.1-1 (Continued)
CHECK TEST CALIBRATE REMARKS CHANNEL DESCRIPTION
- 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 gamma radiation monitors RM-G6, RM-GT, and RM-G8 which are located in high radiation areas of the Reactor Building. These monitors will be calibrated quarterly or at the next scheduled reactor shutdown following g.
dn the quarter in which calibration would normally be due, if a shutdown during the quarter does not occur, j
29 High and Low Pressure Injection NA NA R
Systems: Flow Channels 0
C' CJ f x.)
p*
A.
t TABLE s.1-1 (Continued)
I CHANNEL DESCRIPTION CHECK TEST CALIBRATE REMARKS 30.
Borated Water Storage W
NA R
Tank level Indicator 31.
Boric Acid Mix Tank a.
Level Channel NA NA R
b.
Temperature Channel M
NA R
32.
Reclaimed Boric Acid Storage Tank a.
Level Channel NA NA R
b.
Temperature Channel M
NA R
v 33 Containment Temperature NA NA R
3h.
Incore Neutron Detectors M(1)
NA NA (1) Check functioning; including ibnctioning of computer readout or recorder readout when reactor power is greater than 15%
35 Emergency Plant Radiation M(1)
NA R
(1) Battery check Instruments
- 36. Strong Motion Accelerometer Q(1)
NA Q
(1) Battery check 37 Reactor Building NA NA R
Sump Level L7 C>
CJ b)
...a