ML20071D984
| ML20071D984 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 02/24/1983 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Metropolitan Edison Co, Jersey Central Power & Light Co, Pennsylvania Electric Co, GPU Nuclear Corp |
| Shared Package | |
| ML20071D987 | List: |
| References | |
| DPR-50-A-080 NUDOCS 8303110419 | |
| Download: ML20071D984 (8) | |
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UNIT ED STATES P
NUCLEAR REGULATORY COMMISSION a
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WASHINGTON, D. C. 20555
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METROPOLITAN EDISON COMPANY JERSEY CENTRAL PCWER AND LIGHT COMPANY PENNSYLVANIA ELECTRIC COPFANY GPU NUCLEAR CORPORATION DOCKET NO. 50-289 THREE MILE ISLAND NUCLEAR STATION, UNIT NO. 1 i
AMENDMENT TO FACILITY OPERATING LICENSE 4
Amendment No. 80 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.
I (the licensees), dated November 23, 1981, as modified and supplemented September 3,1981, November 23, 1981, August 11, 1982, and January 5,1983, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the 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 public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the comon i
defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Par't 51 of the Commission's regulations and all applicable requirements have been satisfied.
i 8303110419 830224
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DR ADOCK 05000 I
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.c.(2) of Facility Operating License No. DPR-50 is hereby amanded to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 80, are hereby incorporated in the license. GPU Nuclear Cor-poration shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment becomes effective six weeks after its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Johji F. Stolz, Chief Op6 rating Reactors Branch #4 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: February 24, 1983
e ATTACHMENT TO LICENSE AMENDMENT NO. 80 FACILITY OPERATING LICENSE NO. DPR-50 DOCKET NO. 50-289 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.
. Remove Insert 3-22 3-22 3-23*
3-23
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3-24 3-24 4-7 4-7 4-10 4-10
- 0verleaf page provided to maintain document completeness.
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e.
Core flood tank (CFT) vent valves CF-V3A and CF-V3B shall be closed and the breakers to the CFT vent vqlve motor operators shall be tagged open, except when adjusting core ficod tank level and/or pressure 3.3.1.3 Reactor Building Spray System and Reactor Building Emergency Cooling System 1
The following components must be operable:
a.
Two reactor building spray pumps and their associated spray nozzles headers and two reactor building emergency cooling fans and associated cooling unitt (one in each train).
b.
The sodium hydroxide (NaOH) tank level shall be maintained at 8 feet + 6 inches lower than the BWST level as measured by the BWST/NaOH tank diff' erential pressure indicator. The NaOH tank concentration shall be 10.0 +.5 weight percent (%).
c.
All manual valves in the discharge lines of the sodium hydroxide tank shall be locked open.
3.3.1.4 Cooling Water Systems a.
Two nuclear service closed cycle cooling water pumps must be operable.
b.
Two nuclear service river water pumps must be operable.
c.
Two decay heat closed cycle cooling water pumps must be operable.
I I
d.-
Two decay heat river water pumps must be operable.
e.
Two reactor building emergency cooling river water pumps must be operable.
3.3.1.5 Engineered Saf eguards Valves and Interlocks Associated with the Systems in specifications 3.3.1.1, 3.3.1.2, 3.3.1.3, 3.3.1.4 are operable.
3.3.2 Maintenance shall be allowed during power operation on any l
component (s) in the makeup and purification, decay heat, RB emergency-l cooling water, RB spray, CFT pressure instrumentatlon, CFT level l
instrumentation, BWST level instrumentation, or cooling water systems i
which will not remove more than one train of each system from service.
Components shall not be removed f rom servi,ce so that the af f ected system train is inoperable for more than 72 consecutive hours.
If the system is not restored to meet the requirements of Specifications 3.3.1 within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, the reactor shall be placed in a cold shutdown condition within twelve hours.
Am:ndment No. 3), 80 3-22 l
i 3 3.3 Exceptions to 3 3.2 shall be as follows:
a.
Both core flood tanks shall be operable at all times.
b.
Both the actor operated valves associated with the core flood tanks shall be fully opened at all times.
c.
One reactor building cooling fan and associated cooling unit shall be permitted to be out-of-service for seven days.
.3.3.k Prior to initiating maintenance on any of the components, the duplicate (redundant) component shall be tested to assure operability.
Bases The requirements of Specification 3.3.1 assure that, before the reactor can be made critical, adequate
- engineered safety featuns are operable. Two engineered safeguards makeup pumps, two decay heat removal pumps and two decay heat removal coolers (along with their respective cooling water systems conqponents) an speci fi ed.
However, only one of each is necessary to supply emergency coolant to the reactor in the event of a loss-of-coolant accident. Both core floodin6 tanks are required because a single core flooding tank has insufficient inventory to reflood the core for hot and cold line breaks.
The borated water storage tank is used for three purposes:
A.
As a supply of borated water for accident conditions.(1)
B.
As a supply of borated wate-or flooding the fuel transfer canal during refueling operation. 2 i
C.
As an alternate source of borated water for reaching cold shutdown.(3)
Borated water storage capacity of 350,000 gallons in the BWST is required to -
supply emergency core cooling and reactor building spray in the event of a loss-of-coolant accident.
The borated water storage tank capacity of 360,000 gallons is based on refueling volume requirements. Redundant heaters maintain the borated water supply at a temperature greater than LOOF.
he boron concentration is specified to be in excess of the amount of boron required to maintain the core 1 percent suberitical at 70 F vithout any control rods in the core. his concentration is 1609 ppa boron while the minimum value specified in the tanks is 2.270 ppm boron.
The post-accident reactor building emergency cooling may be accomplished by thne emergency cooling units, by two sprav systems, or by a combinatinn of ona emergency cooling unit and one spray system. The specified requiremente assure that the required post-accident components are available.W 3-23
4 The iodine removal function of the reactor building spray system reouires one spray pump and sodium hydroxide tank contents.
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The spray system utilises common suction lines with the decay heat removal system.
If a single train of equipment is removed frem either system, the other train must be assured to be operable in each system.
When the reactor is critical, maintenance is allowed per Specification 3.3.2 and 3.3.3 provided requirements in Specification 3.3.k are met which assure operability of the duplicate components.
The specified maintenance times are a maximum.
Operability of the specified components shall be based on the results of testing as required by Technical Specification k.5 An allowable maintenance period of up to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> may be utilized if the operability of equipment redundant to that removed from service is demonstrated innediately prior to removal.
In the event that the need for emergency core cooling should occur, operation of one makeup pump, one decay heat removal pump, and both core flood tanks vill protect the core.
In the event of a reactor coolant system rupture their operation vill limit the peak clad temperature to less than 2,300 F and the metal-water reaction to that representing less than 1 percent of the clad.
Two nuclear service river vnter pumps and two nuclear service closed cycle cooling pumps are required for normal operation. The normal operating requirements are greater than the emergency requirements following a loss-of-coolant.
REFERENCES (1) FSAR, Section 1k.2.2.3 (2) FSAR, Section 9.5.2 (3) PEAR, Section'15.3.2 (4) FSAR, Section ik.2.2.3.k m
Amendment No.
80 3-24
a TABLE 4.1-1 (Continued)
CllANNEL DESCRIPTION CllECK TEST CAI.TRRATE RFMARKS 38.
Steam Generator Water 1.evel W
NA R
39.
Turbine Overspeed Trip NA R*
NA D
40.
BWST/Na0li Differentia 1' NA NA R
Pressure Indicator 41.
Sodium Hydroxide Tank Level NA NA R
indicator 42.
Diesel Generator Protective NA NA R
Relaying
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43.
4 KV ES Bus Undervoltage Relays (Diesel Start) a.
Degraded Crid NA M(1)
R (1) Relav operation will be checked I
. by local test pushbuttons b.
loss of Voltage NA M(1)
R (1) Relay operation will be checked by local test pushbuttons 44.
Reactor Coolant Pressure S(1)
M R
(1) When reactor coolant systesi is DH Valve Interlock Bistable pressurized above 300 psia or Taves is greater than 200 F.
45, loss of Feedwater Reactor Trip S(1)
M(1)
R (1) When reactor power exceeds 7%
power 46 Turbine Trip / Reactor Trip S(1)
M(1)
R (1) When reactor power exceeds 20%
power 47.a Pressurizer Code Safety Valve S(1)
R (1)' When T la Freater than 5250F and PORV tailpipe flow monitors
.b PORV - Acoustic / Flow NA M(1)
R (1) When T,,, is greater than 5250F 48 PORV Setpoints NA M(1)
R (1) Per Specification 3.1.12 excluding valve operation.
- Test to be performed prior to exceeding 207, power during Cycle 5 startup only.
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TABLE k.1-3 (Continued)
Ite=
Check Frequency 11.
Deleted l1 12.
Condenser Partition I
Partition Factor Once if primary /
Factor secondary leakage 4
develops, i.e. : Gross Beta-Ca==a on secondary e
side of OTSG i than 2 x 10-0 =s greater iero curies per cc and evidence of fission products is present (1)
When radioactivity level is greater than 10 percent of the li=its of Specification 3.1.L, the sa=pling frequency shall be increased to a mini =u= of 5 times per week.
(2)
E deter =ination vill be started when the 15 =inute gross desassed beta-ga==a activity analysis indicates greater than 10 pCi/=1 and vill be redeten=ined each 10 UCi/=1 increase in the 15 minute gross desassed beta-ga==a activity analysis.
A radio che=ical analysis for this purpose shall consist of a quantitative =easure=ent of 95 percent of radionuclides in reactor coolant with half lives of >30 minutes.
(3)
When the gross activity increases by a factor of two above background, an iodine analysis vill be made and perfor=ed thereafter when the gross activity increases by 10 percent.
Amendmen t No. 62, 80 k-10
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