ML20071K883
| ML20071K883 | |
| Person / Time | |
|---|---|
| Site: | Crane |
| Issue date: | 07/25/1994 |
| From: | Stolz F Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20071K886 | List: |
| References | |
| NUDOCS 9408020069 | |
| Download: ML20071K883 (6) | |
Text
.
98 flIQg 4/
b i
g k
UNITED STATES
((
NUCLEAR REGULATORY COMMISSION f
-f g, v,j WASHtNGTON, D.C. 20555-0001 METROPOLITAN EDISON COMPANY JERSEY CENTRAL POWER & LIGHT COMPANY l
PENNSYLVANIA ELECTRIC COMPANY GPU NUCLEAR CORPORATION DOCKET NO. 50-289 THREE MILE ISLAND NUCLEAR STATION. UNIT NO. 1 BiENDMENT TO FACILITY OPERATING LICENSE i
Amendment No.188 License No. DPR-50 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by GPU Nuclear Corporation, et al.
(the licensee), dated February 10, 1994, 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; j
C.
There is reasonable assurance (i) 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 common 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 Part 51-of the Commission's regulations and all' applicable requirements have been satisfied.
j
\\
o 9408020069 940725 PDR ADOCK 05000289 P
ppg
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 amended to read as follows:
(2) Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No.188, are hereby incorporated in the license. GPU Nuclear Corporation shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance, to be implemented within 30 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
$k&W W
John F.
tolz, Director Project Directorate I-4 Division of Reactor Projects - I/II Office of Nuclear Reactor.tegulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
July 25,1994 e
i I
i
-. _ ~
~-
.i
)
ATTACHMENT TO LICENSE AMENDMENT NO.188 FACILITY OPERATING LICENSE NO. DPR-50 i
DOCKET N3. 50-289 i
Replace the following pages of the Appendix A. Technical. Specifications with the attached pages. The revised pages are identified by amendment number and i
contain vertical lines indicating the area of change.
I
{
Remove Insert i
3-42 3-42 (no change) 3-43 3-43 3-43a (new page)
I 1
.i t
i i
{
l i
I i
l f
l l
e
,,n.
. ~.,.
e r
-]
i
~
3.7 UNIT ELECTRIC POWER SYSTEM i
Aeolicability Applies to the availability of electrical power for operation of the unit auxiliaries.
{
Ob.iective To define those conditions of electrical power availabil'ity necessary to ensure:
a.
Safe' unit operation b.
Continuous availability of engineered safeguards Specification i
3.7.1 The reactor shall not be made critical unless all of the following requirements are satisfied:
a.
All engineered safeguards buses, engineered safeguards switchgear, and engineered safeguards load shedding systems are operable.
b.
One 7200 volt bus is energized.
i c.
Two 230 kv lines are in service, i
d.
One 230 kv bus is in services.
i e.
Engineered safeguards diesel generators are operable and at least 25,000 gallons of fuel oil are available in the storage tank.
f.
Station batteries are charged and in service. Two battery chargers per battery are in service.
i 3.7.2 The reactor shall not remain critical unless all of the following requirements are satisfied:
a.
Two 230 kv lines are in service and capable of carrying auxiliary power to Unit 1, except as specified in Specification 3.7.2e below.
b.
Both 230/4.16 kv unit auxiliary transformers shall be in operation except that within a period not to exceed eight hours in duration from and after the time one Unit I auxiliary transformer is made or found inoperable, two diesel generators shall be operable, and one of the operable diesel generators will be started and run continuously-until both unit auxiliary transformers are in operation. This mode of operation may continue for a period not exceeding 30 days.
In lieu of running a diesel generator, a 4160 volt tie from a Unit 2 transformer shall be placed in service, thus supplying the second of two feeds to the engineered safeguard buses causing no degradation of the system and permitting continued operation indefinitely.
c.
Both diesel generators shall be operable except that from the date l
that one of the diesel generators is made or found to be inoperable 4
3-42 i
A(mendment No. 188 no change)
for any reason, reactor operation is permissible for the succeeding seven days provided that the redundant diesel generator is:
1.
verified to be operable immediately; 2.
within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> either:
a.
determine the redundant diesel generator is not inoperable due to a common mode failure or b.
test redundant diesel generator in accordance with surveillance requirement 4.6.1.a.
In the event two diesel generators are inoperable, the unit shall be placed in hot shutdown in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. If one diesel is not operable within an additional 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period the plant shall be placed in cold shutdown within an additional 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> thereafter.
With one diesel generator inoperable, in addition to the above, verify that: All required systems, subsystems, trains, components and devices that depend on the remaining OPERABLE diesel generator as a source of emergency power are also OPERABLE or follow speci'ications 3.0.1.
d.
If one Unit Auxiliary Transformer is inoperable and a 4160 volt tie from Unit 2 transformer cannot be placed in service and a diesel generator becomes inoperable, the unit will be placed in hot shutdown within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
If one of the above sources of power is not made operable within an additional 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> the unit shall be placed in cold shutdown within an additional 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> thereafter.
e.
If Unit 1 is separated from the system while carrying its own auxiliaries, or if only one 230 kv line is in service, continued reactor operation is permissible provided one emergency diesel generator shall be started and run continuously until two transmission lines are restored.
f.
The engineered safeguards electrical bus, switchgear, load shedding, and automatic diesel start systems shall be operable except as provided in Specification 3.7.2c above and as required for testing.
g.
One station battery may be removed from service for not more than eight hours.
3-43 Amendment No. 98,188
i i
l t
Bases l
The Unit Electric Power System is designed to provide a reliable source of power for balance of plant auxiliaries and a continuously available power
. supply for the engineered safeguards equipment. The availability of the various components of the Unit Electric Power System.dicates the permissibie mode of station operation.
Verification of operability normally consists of verifying that the surveillance is current, and_ that other available information does not l
indicate inoperability.
It is recognized that while testing the redundant diesel in accordance with surveillance requirement 4.6.1.a, the diesel will not respond to an automatic i
initiation signal.
In this situation, the 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> time clock will not be entered per the provisions of section 3.7.2.f. due to the low probability of an event occurring while the diesel being tested.
b l
l r
I l
t t
i
.l i
3-43a Anendment No. 188 1
. - - - -