ML20011E272
| ML20011E272 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 02/01/1990 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | GPU Nuclear Corp, Jersey Central Power & Light Co, Metropolitan Edison Co, Pennsylvania Electric Co |
| Shared Package | |
| ML20011E273 | List: |
| References | |
| DPR-50-A-152 NUDOCS 9002130065 | |
| Download: ML20011E272 (7) | |
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NUCLEAR REGULATORY COMMISSION WASHINOTON, D, C,20566
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METROPOLITAN EDISON COMPANY JERSEY CENTRAL. POWER.4'. LIGHT. COMPANY PENNSYLVANIA ELECTRIC COMPANY L
GPU NUCLEAR CORPORATION 1
DOCKET NO. 50-289 THREE MILE-ISLAND NUCLEAR STATION. UNIT-NO.1 AMENDMENT TO FACILITY OPERATING. LICENSE Amendment No. 152 License No. DPR-50 1.
The Nuclear Regulatory Comission (the Comission) has.found that:
A.
The application for amendment by GPU Nuclear Corporation, et al.
(thelicensee)datedOctober4,1989complieswiththestandudsand requirements of the Atomic Energy Act of 1954,'as amended (the Act),
and the Comission's rules and regulations set forth in 30 CFR Chapter I; B.
The facility will o)erate in conformity with the application, the provisions of t1e Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the p9blic, and (ii) that such activities will be:
conducted in compliance with the Comission's regulations:
D.
- he issuance of this amendment will not be inimical to the comen defense and security or to the health and safety of the public; and E.
Tho issuance of this amendment is in accordance with 10 CFR Part 51 of the'Comission's regulations and all applicable requirements have been satisfied.
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9002130065 900201 PDR ADOCK 05000289 P
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Accordingly, the license -is amended by changes to the Technical t
Specifications as indicated in the attachment to this license 5
amendment, and paragraph 2.c.(2) of Facility Operating License No.,
y DPR-50 are hereby amended to read as follows:
(2) Technical-Specifications-The Technical Specifications contained in Appendix
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L A,-as revised through Amendment No.152 are.
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~hereby incorporat64 in the license. GPU Nuclear L
Cor> oration shall operate the facility in accordance wit) tre Technical Specifications.
3.
This license amendment is effective as of its date of issuance, to be i
implemented within 30 days of issuance.
FOR THE NUCLEAR-REGULATORY COMMISSION
&[,
l J in F. Stolz, Direc r l
P ject Directorate' -4 J vision of Reactor Projects - I/II 3
Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications-Date of Issuance:
Fabruary 1, _ 1990
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ATTACHMENT-TO LICENSE. AMENDMENT.NO.1.52 '
FACILITY.0PERATING LICENSE.NO. DPR '
DOCKET NO. 50-289 4
Replace'the following pages of the Facility Operating License and the Appendix 7
A Technical Specifications with the attached pages. The revised pages are-identified by amendment number and contain vertical lines indicating the area of change.
Remove Insert 3-16 3-16 i
3-20 3-20 l-3-34a 3-34a figure 3.5-2m Figure 3.5-2m-l 9
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MODERATOR TEMPERATURE C0 EFFICIENT OF REACTIVITY k
Acolicability i
Applies to maximum positive moderator temperature coefficient of 1
reactivity at full power conditions.
1 Ob.iective To assure that the moderator temperature coefficient stays within the limits calculated for safe operation of the reactor.
j Specification 3.1.7.1'The moderator temperature coefficient shall not be positivs at power levels above 95% of rated power.
3.1.7.2 The moderator temperature coefficient shall be f +0.9 x l '
10-* ak/k/F at power levels f 95% of rated power.
L Bases A non-positive moderator coefficient at power levels above 95% of rated' power is.specified such that the maximum clad temperatures will not exceed the Final Acceptance Criteria based on LOCA' analyses.
L Below 95% of-rated power the Final Acceptance Criteria will-not be-L exceeded with a-positive moderator temperature coefficient of
+0.9 x 10-* ak/k/F.
All other accident analyses as reported in the j'
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FSAR have been performed for's range of moderator temperature coefficients up to and including +0.9 x 10-* ak/k/F.
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o A non-positive moderator coefficient at power levels above 95% of i
rated power is also required to prevent overpressurization of the reactor coolant system in the event of a feedwater line break (see Specification 2.3.1, Basis C, Reactor Coolant System Pressure).
L The experimental value of the moderator coefficient will-be corrected to obtain the hot full power moderator coefficient.
The Final Acceptance Criteria states that post-LOCA clad temperature will not exceed 2200'F.
REFERENCES (1) UFSAR, Section 14 (2) UFSAR, Section 3 n
3-16 Amendment No. f!f,152 y
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The cuantity of boric acid in storage f om either' of the three above -
s mentioned sources is~ sufficient to borate the reactor coolant system t
1' to a one perc6nt suberitical margin in.the cold condition at th6 m
. worst time in core life with a stuck. control rod assembly. Minimum voluus (including a 10 percent safety factor) of 906 ft* of 8700 ppm boron ~as concentrated beric acid-solution in the boric acid mix tank or in a reclaimed boric acid storage tank or approximately 40,000 gallons of 2270 ppm boron as boric acid solution in the
-l borated water storage tanU *? will each satisfy this requirement.
I The specification assures that at least two of these supplies are available whenever the reactor is critical so that a single failure will. not prevent boration to-a cold condition..The minimum volumes.
of boric acid solution given include the boron necessary to account for xenon decay.
U The primary method of adding boron to the reactor coolant system is to pump the concentrated boric acid solution (8700 ppm boron, minimum) into the makeup tank using either the 10 gmn boric acid pumps or the 30 ppm reclaimed boric acid pumps. Using only one of the two 10 ppm boric acid pumps, the required volume can be injected in less than 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br />. The alternate method of addition is to inject boric acid-from tha borated water storage tank using the makeup and purification pumps.
The 40,000 gallons of boric acid can be injected l.
in less than four hours using only one of the makeup and purification pumps.
Concentration of boron in the boric acid mix tank or a reclaimed boric acid storage tank may be higher than the concentration which would crystallize at ambient conditions.
For this reason, the boric acid mix tank is provided with an imersion electric heating element and tha reclaimed boric acid tanks are provided.with low pressure steam heating jackets to maintain the temperature of their contents well.above (10CF or more) the crystallization temperature of the
-boric acid solution contained in them. Both types of heaters are-p controlled by temperature sensors immersed in the solution contained in the tanks.
Further,_all piping, pumps and valves associated with I.
- the boric acid mix tank and the reclaimed boric acid storage tanks to
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transpo:' boric acid solution from them to the makeup and purification system are provided with redundant electrical heat L
tracing to ensure that the boric acid solution will be maintained 30sF or more above its crystallization temperature. The electrical heat tracing is controlled by the temperature of the external L
surfaces of the piping systems. Once in the makeup and purification
.cystem, the boric acid solution is sufficiently well mixed and diluted so that rormal systern temperatures assure boric acid u
solubility, m
References (1) UFSAR, Sections 9.1 and 9.2 l
(2) UFSAR, figure 6.2 j
(3) Technical Specification 3.3 l
1 l-3-20 Amendment No. EI, 152 L
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7 1.ITheprotection'systemreactorpower/imbalanceenvelope trip setpoints shall be reduced 2 percent in power fcr -
each 1 percent tilt, in excess of the tilt limit or l
when thermal power is equal to or less than 50% full power' with four reactor coolant pumps running set the nuclear-overpower trip setpoint equal to or le,ss than j
-60% full-power..
1 2.
The control rod group withdrawal limits in the CORE ~
L OPERATING LIMITS REPORT shall tHe reduced 2 percent in 3
power'for each 1 percent tilt in excess of the tilt limit.
3.-
Ths operational imbalance limits in the CORE 0PERATING LIMITS REPORT =shall be reduced 2 percent in power for each I percent tilt in excess of the tilt limit.
- f. Except for physics or diagnostic testing, if quadrant tilt is in excess of the maximum tilt limit defined in the CORE-0PERATING LIMITS REPORT and using-the applicable detector system defined in 3.5.2.4.a b, and c above, the reactor-will be placed in the HOT SHUTDOWN condition. Diagnostic testing during power operation with a quairant tilt is s
permitted provided that the thermal power allowable:is restricted as stated in 3.5.2.4.d above.
- g. Quadrant tilt shall be monitored on a minimum frequency of once every two hours during power operation above 15 percent of rated power.
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l Amendment No. J9', 36',.3% JRI, 6, 50',126 126142, IN( 152 i
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