ML20062M276
| ML20062M276 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 12/21/1993 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | GPU Nuclear Corp, Jersey Central Power & Light Co |
| Shared Package | |
| ML20062M280 | List: |
| References | |
| DPR-16-A-167 NUDOCS 9401060380 | |
| Download: ML20062M276 (11) | |
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UNITED STATES
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3 NUCLEAR REGULATORY COMMISSION Ea '
'f WASHINGTON, D.C. 20S55-0001 kw
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GPU NUCLEAR CORPORATION S!!D JERSEY CENTRAL POWER & LIGHT COMPANY DOCKET NO. 50-219 0YSTER CREEK NUCLEAR GENERATING STATION AMENDMENT TO FACILITY OPERATING LI G LS1 Amendment No.167 License No. DPR-16 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by GPU Nuclear Corporation, et al.
(the licensee), dated October 18, 1993, 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 facil;+y 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 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 br e atisfied.
9401060380 931221 PDR ADOCK 05000219 P
h 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-16 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.167, 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 the date of issuance, to be t
implemented within 60 days of issuance.
FOR-THE NUCLEAR REGULATORY COMMISSION'
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Jo
' F. Stolz, Director Pr ect Directorate I-vision of Reactor Projects - 1/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
December 21, 1993 l
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I j
L ATTACHMENT TO LICENSE AMENDMENT NO. 167 FACILITY OPERATING LICENSE N0. DPR-16 DOCKET NO. 50-219
. Replace the following pages of the Appendix A Technical Specifications with the enclosed pages as indicated. The revised pages are. identified by amendment number and contain vertical lines indicating the areas of change.
Remove Insert 1.0-1 1.0-1 3.2-3 3.2-3 3.4-1 3.4-1 3.4-4 3.4-4 3.5-6 3.5-6 3.5-7 3.5-7 3.8-1 3.8-1 3.17-1 3.17-1 1
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SECTION I DEFINITIONS The followino frequently used terms are defined'to aid in the uniform interpre-tation of the specification.
1.1 OPERABLE-OPERABILITY A system, subsystem, train, component, or device shall be OPERABLE or have OPERABILITY when it-is capable of performing its specified function (s).
Implicit in this definition shall be the assumption that all necessary attendant-instrumentation, controls, normal and emergency electrical power sources, cooling of seal water, lubrication or other auxiliary. equipment:that are required for the system, subsystem, train, component or device to perform its function (s) are also capable of performing their related support function (s).
A verification of operability is an administrative check,-by examination of appropriate plant records (logs, surveillance test records) to determine that-a system, subsystem, train, component or device is not' inoperable.
Such verification does not preclude the demonstration (testing) of a given system, subsystem, train, component or device to determine operability.
1.2 OPERATING Operating means that a system or component is performing its required function.
1.3 POWER OPERATION Power operation is any operation when the reactor is in the startup mode or run mode except when primary containment integrity is not required.
1.4 STARTVP MODE The reactor is in the startup mode when the reactor mode switch is in the startup mode position.
In this mode,-the reactor protection system scram trips ' initiated by condenser low vacuum and main steam line isolation valve closure are bypassed when reactor pressure is less.than 600 psig; the low pressure main steamline isolation valve closure is bypassed; the IRM-trips for rod block and scram are operable; and the SRM trips for rod block are operable.
1.5 RVN MODE The reactor is in the run mode when the reactor mode switch.is in the run 1
mode position.
In this mode, the reactor protection system is energized with APRM protection and the control rod withdrawal interlocks are in service.
1.6 SHUTDOWN CONDITION The reactor is in a shutdown condition when the reactor mode switch-is in the shutdown mode position and there is fuel in the reactor vessel.
In this condition, the reactor is suberitical, a control rod block'is-initiated, all operable control rods are fully inserted, and specification 3. 2-A is met.
0YSTER CREEK 1.0-1 Amendment No.: 20, 44, 64, 167.
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2.
-The standby liquid control solution shall have a Boron-10 isotopic enrichment equal to or greater than 35 atom %, be 4
maintained within the cross-hatched volume-concentration requirement area in Figure 3.2-1 and at a' temperature not
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less than the temperature presented in Figure 3.2-2 at all i
times when the standby liquid control system is required to be operable.
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3.(a)
If one standby liquid control system pumping circuit becomes inoperable during the RUN mode and Specification 3.2.A is met, the reactor may remain in operation for a period not to exceed 7 days, provided the pump in the.
other circuit is verifie6 daily to be operable, otherwise be in the Shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
j (b'
If the solution is outside the cross-hatched h
volume-concentration area but within the shaded volume-concentration area of Figure 3.2-1, return the solution to the ' cross-hatched area within days. -If, after this time period, the requirement is still not met, submit a report to the NRC within 7 days advising them of plants to return the solution to the cross-hatched volume-concentration area.
(c)
If the solution is outside the cross-hatched volume concentration area and outside.the shaded volume-concentration area of Figure 3.2-1, return the solution to within the shaded volume-concentration area of Figure 3.2-1 or be in the Shutdown condition within 24-hours.
(d)
If the solution temperature is less than the minimum shown in Figure 3.2-2, increase the temperature to greater than-the minimum and verify the solution is within the-shaded volume-concentration area of Figure 3.2-1 or be in the Shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
(e)
If the enrichment requirement of 3.2.C.2 is not met:
(1) Return the Boron-10 isotopic enrichment'to greater than or equal to 35 atom % within 7 days of the receipt of the enrichment report.
If, after this time period, the enrichment requirement.is still not met, submit a report to the NRC within 7 days advising them of the plans to return the' solution to greater than. or equal to 35 atom % Boron-10 isotopic enrichment.
(2) A check shall be made to ensure that-the sodium.
pentaborate solution meets the original design criteria by comparing _the enrichment, concentration and volume to established criteria (Beron-10 equal to or greater than 82 pounds).
If the sodium pentaborate; solution does not meet the original criteria,;be in the Shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
0YSTER CREEK 3.2-3 Amendment No:'75,. W, 167,.
3.4 EMERGENCY COOLING-Acolicability:
-Applies to the operating status of the emergency cooling-systems.
Ob.iective:
To assure operability of the emergency cooling systems.
Soecifications:
A.
.C_ pre Soray System 1.
The core spray system shall be operable at all times with -
irradiated fuel in the reactor vessel, except as otherwise-specified in this section.
2.
The absorption chamber water volume shall be at least 82,000 ft.3 in order for the core spray system to be considered operable.
3.
If one core spray system loop or its core spray header delta P instrumentation becomes_ inoperable during the run mode, the reactor may remain in operation for a period not to exceed 7 days (See Note below) provided:
a.
The remaining loop has no inoperable' components and is verified daily to be operable and, b.
The average planar linear heat generation rate (APLHGR) of all the rods in any fuel assembly, as a function o average planar exposure, at any axial location shall not exceed 90% of the limits given in Specification 3.10.A.
The action to bring the core to 90% of the APLHGR Limits must be completed within two-hours after the systerr has been determined to be inoperable.
- 4. The reactor may remain in operation for a period not to exceed 15 days if one of the redundant active loop components in the core-spray system becomes inoperable during the run mode provided:
a.
In the event of an inoperable core spray booster pump, the otiar core spray booster pump in the loop is verified daily to be operable, b.
In the event of an inoperable core spray main pump, the other-core spray main pump in the loop is verified daily to be operable and the APLHGR of-all the rods in any fuel assembly, as a function of average planar exposure, at any axial location shall not exceed 90% of the limits given in Specification 3.10.A.
The action to bring the core to 90% of the APLHGR Limits must be' completed within two hours after the component has been determined to be inoperable.
0YSTER CREEK 3.4-1 Amendment No.: 84, dif3',167
automatic depressurization function) may be. inoperable or bypassed during the system hydrostatic pressure test required by ASME Code Section XI,15-500 at or near the end of each ten year.
inspection interval.
- 2. If at any time there are only four operable electromatic relief valves, the reactor may remain in operation for.a period not to exceed 3 days provided the motor operated isolation and condensate makeup valves in both isolation condensers are verified daily to be operable.
- 3. If Specifications 3.4.B.1 and 3.4.B.2 are not met; reactor pressure shall be reduced to 110 psig or less, within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
- 4. The time delay set point for initiation after coincidence' of low-low-low reactor water level and high drywell pressure shall be set not to exceed.two minutes.
C.
Containment Soray System and Emeraency Service Water System
- 1. The containment spray system and the emergency service water.
system shall be operable at all times with irradiated fuel in the reactor vessel, except as specified in Specifications 3.4.C.3, 3.4.C.4, 3.4.C.6 and 3.4.C.8.
- 2. The absorption chamber water volume shall not be le'ss than 82,000 ft in order for the containment spray and emergency service water system to be considered operable.
- 3. If one emergency service water system loop becomes inoperable,-
its associated containment spray system loop shall be considered inoperable.
If one containment. spray system loop and/or its-associated emergency service water system loop becomes inoperable during the run mode, the reactor may remain in
)
operation for'a period not to exceed-7 days provided the-remaining containment spray system loop and its associated emergency service water system loop.each have no inoperable components and are verified daily to be operable.
4.
If a pump in the containment spray system or emergency. service water system becomes. inoperable, the re&ctor may remain in operation for a period not to exceed 15 days provided the other similar pump is verified daily to' be. operable.
A maximum of two pumps may be inoperable provided the two pumps are not in the--
same loop.
If more than two pumps become inoperable, the limits..
of Specification 3.4.C.3 shall apply.
- 5. During the period when one diesel is inoperable, the containment spray loop and emergency service water system loop.
conn.ected to the operable diesel shall; have no inoperable components.
- 6. If primary containment integrity is not required (see Specification 3.5. A), the. containment spray system may be made inrperable.
1 OYSTER CREEK 3.4-4 Amendment No.: #$,(ff,167--
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1.1 Upon the accidental loss of secondary containment integrity, restored secondary containment integrity within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, or:
a.
During Power Operation:
(1)
Have the reactor mode switch in the shutdown mode position within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
(2)
Cease all work on the reactor or its-connected systems in the reactor building which could result in inadvertent releases of radioactive-materials.
(3)
Cease all operations in, 'above or' around the Spent Fud Stora99 Pool that could cause' release of radioactive materials.
b.
During refueling:
(1)
Cease fuel handling operations or activities which could reduce the :hutdown margin (excluding resctor coolant temperature' changes).
(2)
Cease all work on the reactor or its connected.
systems in the reactor building which could result in inadvertent releases of radioactive materials.
(3)
Cease all operations in, above or around the Spent Fuel Storage Pool that could cause release of radioactive materials.
2.
Two separate and independent standby gas treatment system circuits shall be operable when secondary containment is required except as specified by Specifi-cation 3.5.B.3.
3.
With one standby gas treatment' system circuit inoperable:
a.
During Power Operation:
(1)
Verify the operability of the other standby gas treatment system. circuit within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. If testing is required to demonstrate operability and significant painting, fire, or chemical-release has taken place in the reactor building within the previous 12-hours, then demonstration-by testing shall take place within I hour of the expiration of the 12 hour-period,:and' (2)
Continue to verify the operability of the standby gas treatment system circuit once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> until the inoperable-standby gas treatment circuit is returned to operable status.
0YSTER CREEK 3.5-6 Amendment No.: I4/1848fl/4(Ids.
- 167,
w (3)
Restore the inoperable standby gas treatment
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circuit to operable status within 7 days or be subtritical with reactor coolant tempera-ture less than 212"F within the next 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />, b.
During Refueling:
a (1)
Verify the operability of the other standby gas treatment system circuit within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. If testing is required to demonstrate. operability and significant painting, fire, or chemical release has taken place in the reactnr building within the previous 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, then demonstration =
by testing shall take place ~within I hour of the expiration of the.12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> period, and (2)
Continue to verify the operability of the redundant standby gas treatment system once per 7 days until the inoperable system is returned to operable status.
(3)
Restore the inoperable standby gas treatment system to operable status within 30 days or.
cease all spent fuel handling, core altera-tions or operation that could reduce the shutdown margin (excluding reactor coolant temperature changes).
4.
If Specifications 3.5.B.2 and 3.5.B.3 are not met, reactor shutdown shall be initiated and the reactor shall be in the cold shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and the condition of Specification 3.5.B.1 shall be met.
Bases:
Specifications are placed on the operating status of the containment systems-to assure their availability to control the release of any radioactive materials from irradiated fuel in the event of an accident condition.- The ~~
primary containment system (1) provides a barrier against uncontrolled release of fission' products to the environs in the event of a break in the reactor coolant systems.
Whenever the reactor coolant water temperature is above:212*F,.~ failure of-'
the reactor coolant system would cause rapid expulsion of--the coolant-from -
the reactor with.an associated. pressure rise in the primary containment.
Primary containment is required, therefore, to contain the thermal energy of the expelled coolant and fission products which could be released from.any fuel failures resulting from the accident.
If.the reactor coolant is not above 212*F, there would be no. pressure rise in the containment'.
In-addition, the coolant cannot be expelled at a rate which could cause fuel-failure to occur before the core spray system restores cooling to the core.
Primary containment is not needed while performing low power physics tests since procedures and the Rod Worth Minimizer would limit OYSTER CREEK 3.5-7 Amendment No.: 44/84/,88 4 68,
- 161,
3.8 ISOLATION CONDENSER-Acolicability:
Applies te operating status of the isolation condenser.
Obiective:
To assure heat removal capability under conditions of reactor vessel isolation from its normal heat sink.
Specification:
A. The two isolation condenser loops shall be operable during power operations and whenever the reactor coolant temperature is greater than 212 F except as specified in C, below or during reactor vessel pressure testing.
B. The shell side of each condenser shall contain a minimum water volume of 22, 730 gallons.
If the minimum volume cannot be maintained or if a source of makeup water is not available to the condenser, the condenser'shall be considered inoperable.
C. If one isolation condenser becomes inoperable during-the run mode the reactor may remain in operation for a period not to exceed 7 days provided the motor operated isolation and condensate makeup ' valves in the operable isolation condenser are verified daily to be operable.
D. If Specification 3.8. A and 3.8.B are not met, or if an inoperable isolation condenser cannot be repaired within 7 days, the reactor shall be placcd in the cold shutdown condition.
E. If an isolation condenser inlet (steam side) isolation valve (V-14-30, 31, 32 or 33) becomes or is made inoperable,-in the open position during the run mode, the. redundant inlet isolation valve shall be ver_ified operable.
If the inoperable valve is not returned to service within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> declare the affected isolation condenser inoperable, isolate it and comply with Specification 3.8.C.
F. If an AC motor-operated isolation condenser outlet (condensate return) isolation valve (V-14-36 or 37) becomes or is-made inoperable in the open position in the run mode,-return the valve to service within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or declare'the affected isolation condenser inoperable, isolate it and comply with Specification-3.8.C.
Basis:
The purpose of the isolation condenser is to depressurize the reactor and to remove reactor decay heat in the event that-the turbig generator and main condenser is unavailable as_ a heat sink.
Since the shell side of the isolation condensers operate at atmospheric pressure, they can accomplish their purpose when the reactor temperature is sufficiently above 212"F to provide for the heat transfer corresponding to reactor decay heat.
The tube side of the isolation condensers form a closed loop with the reactor vessel and can operate without reducing the reactor coolant water inventory.
0YSTER CREEK 3.8-1 Amendment No.: II, ffd, 167
'3.17 Control room Heatino. Ventilatino, and Air-Conditionino System Acolicability:
Applies to the operability of the control room heating, ventilating, and air conditioning (HVAC) system.
Ob.iective:
To assure the capability of the control room HVAC system to i
minimize the amount of radioactivity from entering the control room in the event of an accident.
Soecification:
A.
The control room HVAC system shall be operable during all modes of plant operation.
B.
With the control room HVAC system determined inoperable:
i 1.
Verify once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> the partial recirculation mode of operation for the operable system, or place the operable system in the partial recirculation mode; and 2.
Restore the inoperable system within 7 days, or
~,.
prepare and submit a special report to.the-Commission in lieu of any other report required by Section 6.9, within the next 14 days, outlining the action taken, the cause of the inoperability and the plans / schedule for restoring the HVAC system to operable status.
C.
With both control room HVAC systems determined inoperable.
1.
During Power Operation: place the reactor in.the cold shutdown condition with 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> q
2.
During Refueling:
(a)
Cease irradiated fuel-handling operations; and (b)
Cease all work on the reactor or its connected systems in the reactor building which could result in inadvertent releases of radioactive materials.
3 Basis:
The operability of the control room HVAC system ensures that the control room will remain habitable for operations personnel during a postulated design' basis accident. The control room envelope.
includes the control room panel area, the. shift supervisor's office.
toilet room, kitchen, and lower cable spreading room.
Since Systems 1
A and B do not have HEPA filters or' charcoal absorbers, the supply fan and dampers for each system minimize the beta and gamma doses to the operators by providing positive pressurization and limiting the makeup and infiltration air into the control. room envelope. 'For the supply of 100% outside air to the control room envelope, the dose-increase to 29.1 rem beta and 3.14 rem gamma for the assumed-30 days, however, these values are within the allowable limits.
OYSTER CREEK 3.17-1
' Amendment No.: II$,(fij,167 0
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