ML20212H899
| ML20212H899 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 06/21/1999 |
| From: | Bajwa S NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20212H904 | List: |
| References | |
| NUDOCS 9906280196 | |
| Download: ML20212H899 (14) | |
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4 UNITED STATES l
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,j NUCLEAR REGULATORY COMMISSION
- $~g WASHINGTON, D.C. 20555 0001 o
METROPOLITAN EDISON COMPANY JERSEY CENTRAL POWER & LIGHT COMPANY PENNSYLVANIA ELECTRIC COMPANY i
GPU NUCLEAR. INC.
DOCKET NO. 50-289
)
THREEjilLE ISLAND NUCLEAR STATION. UNIT NO.1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 212 License No. DPR-50 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by GPU Nuclear, Inc. et al., (the licensee),
dated February 7,1997, as supplemented October 24,1998, 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: (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 j
. E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the l
Commission's regulations and all applicable requirements have been satisfied.
DR DR P
u...
. 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 ree.d as follows:
(2)
Technical Specifications The Technical Specifications contained in Appendices A, as revised through Amendment No. 212, are hereby incorporated in the license. GPU Nuclear, Inc. shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of issuance, to be implemented within 30 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION 4
S. Singh hjwa, Chief, Section 1 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance: June 21, 1999 4
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ATTACHMENT TO LICENSE AMENDMENT NO. 212 FACILITY OPERATING LICENSE NO. DPR-50 DOCKET NO. 50-289 Replace the following pages of the Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by Amendment number and contain marginal lines indicating the areas of change.
Remove Insert i
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3-42 3-42 e
3-43 3-43 4-Sa 4.Sa 4-6 4-6 4-38 4-38 4-38a 4-39 4-39 4-43 4-43 5-8 5-8 5-9 5-9 6-3 6-3 l
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DESIGN FEATURES 51 5.1 SlH -
5-1 5.2 CONTAINMENT 5-2 5.2.1 REACTOR BUILDING 5-2 5.2.2 REACIOR BUILDING ISOLATION SYSTFM 5-3
-5.3 REACTOR 5-4 I
5.3.11 REACTOR CORE 5-4 5.3.2-REACTOR COOLANT SYSTEM 5-4 5.4 NEW AND SPENT FUEL STORAGE FACILITIES 5-6 5.4.1 NEW FUEL STORAGE 5-6 5.4.2
' SPENT FUEL STORAGE 5-6 5.5 AIR INTAKE TUNNEL FIRE PROTECTION SYSTEMS 5-8 6
ADMINISTRATIVE CONTROLS 6-1 6.1 RESPONSIBILITY 6-1
-6.2 ORGANIZATION 6-1 6.2.1 CORPORATE 6-1 6.2.2 UNIT STAFF 6-1 6.3 UNIT STAFF OUALIFICATIONS 6-3 6.4 IIMINING 6-3 6.5 REVIEW AND AUDIT 6-3 6.5.1 TECHNICAL REVIEW AND CONTROL 6-4
.6.5.2 INDEPENDENT SAFETY REVIEW 6-5 6.5.3-AUDITS 6-7 l
-6.5.4 INDEPENDENT ONSITE SAFETY REVIEW GROUP 6-8 6.6 REPORTABLE EVENT ACTION 6-10 6.7
' SAFETY LIMIT VIOLATION 6-10 6.8 PROCEDURES AND PROGRAMS 6-11 6.9 REPORTING REOUIREMENTS 6 12 6.9.1 ROUTINE REPORTS -
6-12 l
6.9.2
. DELETED 6-14
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6.9.3 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 6-17 i
6.9.4 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 6 18
-6.9.5 CORE OPERATING LIMITS REPORT -
6-19 6.10 RECORD RETENTION 6 20
' 6.11 '
RADIATION PROTECTION PROGRAM 6-22 6.12 <
HIGH RADIATION AREA 6-22
' 6.13 -
PROCESS CONTROL PROGRAM 6-23 6.14 :
OFFSITE DOSE CALCULATION MANUAL (ODCM) 6-24 6.15.
DELETED 6-24 6.16 ~
POST ACCIDENT SAMPLING PROGRAMS 6-24 NUREG 0737 (II.B.3. II.F.1.2),
l 6.17 MAJOR CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS 6-25
-V=
Amesulment No.II ;47 ;72 ;77-129,I5h+74,. 212,
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3.7 UNIT ELECTRIC POWER SYSTEM Anolicability Applies to the availability of electrical power for operation of the unit auxiliaries.
Obiective
- To define those conditions of electrical power availability necessary to ensure:
l a.
Safe unit operation b.
Continuous availability of engineered safeguards Specificauon 3.7.1 The reactor shall not be made critical unless all of the following requirements are satisfied:
j All engineered safeguards buses, engineered safeguards switchgear, and engineered safeguards a.
load shedding systems are operable, b.
One 7200 volt bus is energized.
3
.l c.
Two 230 kv lines are in senice.
d.
. One 230 kv bus is in senices.
1 Engineered safeguards diesel generators are operable and at least 25,000 gallons of fuel oil are e.
available in the storage tank.
f.
Station batteries are charged and in senice. Two battery chargers per battery are in senice..
3.7.2 The reactor shall nd remain critical unless all of the following requirements are satisfied:
- Two 230 kv lines are in senice and capable of carrying auxiliary power to Unit 1, except as a.
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 1
not to exceed eight hours in duration from and aAct 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 staned and run continuously until both unit auxiliary transformers are in operation. This mode of operation may continue for a period not exceeding 30 days.
Both diesel generators shali be operable except that from the he that one of the diesel c.
- generators is made or found to be inoperable 3-42 j.'
Arnendment No. 488', 212 l.
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for any reason, reactor operation is pennissible 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 inopen41e, in addition to the atnve, 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 specifications 3.0.1.
- d. '
If one Unit Auxiliary Transformer is inoperable 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.
If Unit 1 is separated from the system while carrying its own auxiliaries, or if only one 230 kv c.
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 sersice for not more than eight hours.
'343 Amendment No.98,488, 212 4
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g 4.4.4 Hvdrocen Recombiner Svstem
. Aeolicability Applies to the testing of the hydrogen recombiner and associated controls.
Obiective To verify that the hydrogen recombiner and associated controls are operable.
4.4.4.1 Soccification
- a. Perfonn a system functional test for each hydrogen recombiner each refueling intenal as follows:
(1) Verify that the muumum heater sheath temperature increases to 2 700'F in s 90 mmutes.
(2) After reaching 700'F, increase the power to maximum for approximately 2 minutes and verify the power to be 2 60kW.
- b. Visually examme the hydrogen recombiner enclosure and verify there is no evidence of abnormal conditions each refueling interval.
- c. Perform a resistance to ground test for each heater phase each refueling interval and verify that the resistance to ground for any heater is 210,000 ohms.
Bases The surveillance program described above provides high assurance that the hydrogen recombiner system will be available to perform its post-LOCA function of maintaining the contamment hydrogen concentration below 4.1 volume percent. This system is not credited to mitigate any accident analyzed in Chapt.cr 14 of th TMI-l FSAR. The frequency of the surveillance of the hydrogen recombiner system is based on the safe significance of the system. TMI-l FSAR Section 6.5.3.1 indicates that the hydrogen recombiner system is not required until 9.0 days'following a LOCA. This is adequate time to place a l
hydrogen recombiner in senice.
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i 4-38 l
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Amendment No.M.48,M4, as, 212
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1 4.5 EMERGENCY LOADING SEOUENCE AND POWER TRANSFER. EMERGENCY CORE COOLING SYSTEM & REACTOR BUILDING COOLING SYSTEM PERIODIC TESTING 4.5.!
Emergency Loading Sequence Aeolicability:
Applies to periodic testing requirements for safety actuation systems, Obiective:
- To verify that the emergency loading sequence and automatic power transfer is operable.
Specifications:
4.5.1.1 Seouence and Power Transfer Test -
During each refueling inten.tl, a test shall be conducted to demonstrate that the a.
emergency loadmg sequence and power transfer is operable.
I b.
The test will be considered satisfactory d the following pumps and fans have been
- I successfully staned and the following valves have completed their travel on preferred power and transferred to the emergency power.
-M. U. Pump
)
-D. H. Pump and D. H. Injection Valves and D. H. Supply Valves
-R. B Cooling Pump
-R. B. Ventilators D. H. Closed Cycle Cooling Pump
-N. S. Closed Cycle Cooling Pump
-D. H. River Cooling Pump
-N. S. River Cooling Pump
-D. H. and N. S. Pump Area Cooling Fan
-Screen House Area Cooling Fan _
4
-Spray Pump. (Initiated in coincidence with a 2 out of 3 R. B.
30 psig Pressure Test Signal.)
-Motor Driven Emergency Feedwater Pump Following successful transfer to the emergency diesel, the diesel generator breaker will c.
be opened to simulate trip of the generator then re-closed to verify block load on the reclosure.
4.5. I.'2 Seauence Test
- a. At intervals not to exceed 3 months, a test shall be conducted to demonstrate that the emergency loadmg sequence is operable, this test shall be performed on either preferred power or emerrney power.
- b. The test will be considered satisfactory if the pumps and fans listed in 4.5.1.lb have been successfully started and the valves listed in 4.5.1. lb have completed their travel.
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Amendment No. -30. 38. 440. M3., 212 l
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' REACTOR BUILDING COOL $iNG AND ISOLATION SYSTEM 4.5.3 Aeolicability Applies to testing of the reactor building cooling and isolation systems, Obiective t To verify that the reactor building cooling systems are operable.
Soccification 4.5.3.1 -
System Tests a.
Reactor Buildinn Sorav System f
- 1. -
At each refueling interval, a reactor building 30 psi high pressure test signal will start the spray pump. Except for the spray pump ;uction valves, all l
engineered safeguards spray valver will be closed.
l i
Water will be circulated from the borated water storage tank through the j
reactor building s, pray pumps and retumed through the test line to the borated water storage tanx.
The operation of the spray valves will be verified during the component test of the R. B. cooling and isolation system.
l T he test will be considered satisfactory if the spray pumps have been racessfully started.
l 2.
Compressed air will be introduced into the spray headers to verify each spray nozzle is unobstructed at least every ten years.
- b. Reactor Buildinn Cooline and Isolation 5'2m1 i
l 1.
During each refueling period. a system test shall be conducted to demonstrate proper operation of the system. A test signal will actuate the Reactor Building Emergency Cooling System valves to demonstrate operability of the coolers.
2.
The test will be considered satisfactory if the valves have completed their expected travel.
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' Amendment No. M*, #8, 212 L
5.5 AIR INTAKE TUNNEL FIRE PROTECTION SYSTEMS Deleted
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Amendment No. 212 5-9 Revised (l-20 76) 9
p Gl.p 6 3 UNIT STAFF OUALIF1 CATIONS 6 3.1 Each member of the unit staff shall meet or exceed the minimum qualifications of ANSI /ANS 3.1 L
l
' of 1978 for comparable positions unless otherwise noted in the Technical Specifications. Licensed l operators shall also meet the requirements of 10 CFR Pan 55. Individuals who do not meet
. ANSI /ANS 3.1 of 1978 Section 4.5, are not considered technicians or maintenance personnel for purposes of determining qualifications but are permitted to perform work for which qualification has been demonstrated..
' 6.3.2 The management position responsible for radiological controls shall meet or exceed the
- qualifications of Regulatory Guide 1.8 of 1977. Each radiological controls technician / supervisor shall meet or exceed the qualifications of ANSI-N 18.1 1971, paragraph 4.5.2/4.3.2, or be l
' formally qualified through an NRC approved TMI-1 Radiation Controls training program. All radiological controls technicians will be qualified through training and examination in each area or specific task related to their radiological controls functions prior to their performance of those tasks.
6.3.3 The Shift Technical Advisors shall have a bachelor's degree or equivalent in a scientific or engineering discipline with specific trairdng in unit design. response and analysis of transients and accidents.
' 6.4 TRAINING 6.4.1 A retrauung and replacement training program for the unit staff shall be maintained under the direction of the plant trauung manager and shall meet or exceed the requirements and recommendations of Regulatory Guide 1.8 of 1977. Licensed operator training shall also meet the requirements of 10 CFR Part 55, 6.4.2. A ' training program for the Fire Brigade shall be maintained and shall meet or exceed the -
requirements of Section 27 of the NFPA Code 1976.
. 6!5 REVIEW AND AUDIT s
- 6.5.1 TFHNICAL REVIEW AND CONTROL
- "Ihe Vice President of each division within GPU Nuclear, Inc. shall be responsible for ensuring the preparation, review, and approval of documents required by the activities described in 6.5.1.1 through
' 6.5.1.5 within his functional area of responsibility as assigned in the GPU Nuclear, Inc. Review and -
Approval Matrix. Implementing approvals shall be performed at the cognizant manager level or above.
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. 63-2 Amendment Nos'.JJ.32.35,77,92,128,13J,132,139,+ MAG 7, 212 I
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