ML20237C365
| ML20237C365 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 08/17/1998 |
| From: | Thomas K NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20237C366 | List: |
| References | |
| NUDOCS 9808210116 | |
| Download: ML20237C365 (7) | |
Text
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UNITED STATES j
NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20066 4 001
/
UNION ELECTRIC COMPANY CALLAWAY PLANT. UNIT 1 DOCKET NO. 50-483 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.127 License No. NPF-30 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Union Electric Company (UE, the licensee) dated March 9,1998, as supplemented by letter dated July 8,1998, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the l
Act, and the rules and regulations of the Commission; l
)
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 l
security or to the health and safety of the public; and l
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.
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. NPF-30 is hereby amended to read as follows:
1 9808210116 980817 l
PDR ADOCK 05000403 l
p PDR l
- (2)
Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No.127 and the Environmental Protection Plan contained in Appendix B, tire hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This amendment is effective as of its date of issuance to be implemented within 30 days from the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION lb.f 44jyA 0 LW M Kristine M. Thomas, Project Manager Project Directorate IV-2 Division of Reactor Projects lil/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance:
August 17, 1998 l
l 1
'n ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO. 127 TO FACILITY OPERATING LICENSE NO. NPF-30 DOCKET NO. 50-483 Replace tX following pages of the Appendix A Technical Specifications with the enclosed pages. The revised pages are identified by amendment number and contain vertical lines indicati.sg the areas of change. The corresponding overleaf pages are also provided to maintain document completeness.
REMOVE INSERT 3/4 5 4 3/4 5-4 B 3/4 5-4 8 3/4 5-4 l
i
I Mt H(it.NCY CORI C00llNG $YblLM5 3 /4. 5. 2 ECCS SUBSYSTEMS - T,,q 1350'F -
LIMITING CONDITION FOR OPERATION 3.5.2 Two independent Emergency Core Cooling System (ECCS) subsystems shall be OPERABLE with each subsystem comprised of:
1 a.
One OPERABLE centrifugal charging pump, f
b.
One OPERABLE Safety Injection pump, 1
c.
One OPERABLE RHR heat exchanger, d.
~
e.
An OPERABLE flow path capable of taking suction from the refueling water storage tank on a Safety Injection signal and automatically transferring suction to the containment sump during the recirculation phase of operation.
APPLICABILITY:
MODES.1, 2, and 3.*
ACTION:
4.
With one ECCS subsystem inoperable, restore the inoperable subsystem to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, b.
In the event the ECCS is actuated and injects water into the Reactor Coolant System, a Special Report shall be prepared and submitted to the Commission pursuant to Specification 6.9.2 within 90 days describ-ing the circumstances of the actuation and the total accumulated actuation cycles to date.
The current value of the usage factor l
f or each af fected Safety injection nozzle shall be provided in this Special Report whenever its value exceeds 0.70.
i 1
- llu provi. inn of.specif ications 3.0.4 and 4.0.4 are not applicable f or entry into M001
.4 f or the r.entrifugal charging pump and the Safety injection pumps als e:1.ireil inops.rable pursuant to Specification 4.5.3.2 provided the centrifugal charging pump and the Safety injection pumps are restored to OPERABLE status within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> prior to the temperature of one or more of the RCS cold legs exceeding 375'F.
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r.Al.l.AWAY UNil 1 3/4 5-3 I
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EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE REQUIREMENTS 4.5.2 Each ECCS subsystem shall be demonstrated OPERABLE:
a.
At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by verifying that the following valves are in the indicated positions with power to the valve operators removed:
Valve Number Valve Function Valve Position BN-HV-8813 Safety injection to Open RWST Isolation Viv-EM-HV-8802A(B)
SI Pump Discharge Closed Hot Leg Iso Vivs EM-HV-8835 Safety Injection Open Cold Leg Iso Valve EJ-HV-8840 RHR/SI Hot Leg Closed Recirc Iso Valve EJ-HV-8809A RHR to Accum Inj Open Loops 1 & 2 Iso Viv EJ-HV-8809B RHR to Accum Inj Open Loops 3 & 4 Iso Viv b,
At least once per 31 days by:
1)
Verifying that the ECCS piping is full of water by venting the RHR and SI pump casings and accessible ECCS discharge piping l
high points, and 2)
Verifying that each valve (manual, power-operated, or automatic) in the flow path that is not locked, sealed or otherwise secured in position, is in its correct position.
c.
By a visual inspection which verifies that no loose debris (rags, trash, clothing, etc.) is present in the containment which could be transported to the containment sump and cause restriction of the aump suctions during LOCA conditions. This visual inspection shall
)e performed:
1)
For all accessible areas of the containment prior to establishing CONTAINMENT INTEGRITY. and 2)
Of the areas affected within containment at the completion of each containment entry when CONTAINMENT INTEGRITY is established.
d.
At least once per 18 nonths by:
'1)
Verifying automatic isolation action of the RHR System from the Reactor Coolant System by ensuring that, with a simulated or actual Reactor Coolant System pressure signal greater than or equal to 425 psig, the interlocks prevent the valves from being opened.
CALLAWAY - UNIT 1 3/4 5-4 Amendment No. 43.127
1 EMERGENCY CORE COOLING SYSTEMS BASES ECCS SUBSYSTEMS (Continued)
The centrifugal charging pump maximum total pump flow Surveillance Requirement ensures the maximum injection flow limit of 550 gpm is not exceeded.
This value of flow is comprised of the total flow to the four branch lines of 469 gpm and a seal injection flow of 79 gpm plus 2 gpm for instrument uncertainties.
The safety injection pump maximum total pump flow Surveillance Requirement ensures the maximum injection flow limit of 675 gpm is not exceeded.
This value of flow includes a nominal 30 gpm of mini-flow.
The test procedure places requirements on instrument accuracy (20 inches of water column for the charging branch lines and 10 inches of water column for the safety injection branch lines) and setting tolerance (30 inches of water column for both the charging and safety injection branch lines) such that branch line flow imbalance remains within the assumptions of the safety analyses.
The maximum and minimum potential pump performance curves, in conjunction with the maximum and minimum flow Surveillance Requirements, the maximum total system resistance, and the test procedure requirements, ensure that the assumptions of the safety analyses remain valid.
The surveillance flow and differential pressure requirements are the Safety Analysis Limits and do not include instrument uncertainties.
These instrument uncertainties will be accounted for in the surveillance test procedure to assure that the Safety Analysis Limits are met.
The Surveillance Requirements for leakage testing of ECCS check valves ensure that a failure of one valve will not cause an inter-system LOCA. The
. Surveillance Requirement to vent the RHR and SI pump casings and accessible, i.e.
can be reached without personnel hazards or high radiation dose. ECCS i
discharge piping ensures against inoperable pumps caused by gas binding or l
water hammer in ECCS piping.
3/4.5 5 REFUELING WATER STORAGE TANK The OPERABILITY of the refueling water storage tank (RWST) as part of the ECCS ensures that a sufficient supply of borated water is available for injection by the ECCS in the event of a LOCA.
The limits on RWST minimum volume and boron concentration ensure that:
(1) sufficient water is available within containment to permit recirculation cooling flow to the core, and (2) the reactor will remain subcritical in the cold condition following mixing of the RWST and the RCS water volumes assuming all the control rods are out of the core. These assumptions are consistent with the LOCA analyses.
CALLAWAY - UNIT 1 B 3/4 5-3 Amendment No. 42-68.127
o Revised by NRC Letter dated:
May 3, 199S EMERGENCY CORE COOLING SYSTEMS BASES REFUELING WATER STORAGE TANK (Continued)
The contained water volume limit includes an allowance for water not usable because of tank discharge line location or other physical characteristics.
The limits on contained water volume and boron concentration of the RWST also ensure a minimum equilibrium sump pH of 7.1 for the solution recirculated within containment after a LOCA. This pH level minimizes the evolution of iodine and minimizes the effect of chloride and caustic stress corrosion on mechanical systems and components.
CALLAWAY - UNIT 1 B 3/4 5-4 Amendment N_o.-"?,SS,96