ML17244A830
| ML17244A830 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 08/24/1979 |
| From: | Ziemann D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17244A831 | List: |
| References | |
| TASK-10, TASK-RR NUDOCS 7909210383 | |
| Download: ML17244A830 (10) | |
Text
UNITED STATES NUCLEAR R EG ULATORY COMMISSION WASHINGTON, O. C. 20555 ROCHESTER GAS AND ELECTRIC CORPORATION DOCKET NO. 50-244 R.
E.
GINNA NUCLEAR POWER PLANT AMENDMENT TO PROVISIONAL OPERATING LICENSE Amendment No. 29 License No.
DPR-18 1.
The Nuclear Regulatory Commission (the Commission) has found that:
B.
C.
D.
E.
The application for amendment by Rochester Gas and Electric Corporation (the licensee) dated February 1, 1977, complies with the standards and requirements of the Atomic Enerqy Act of 1954, as amended (the Act),
and the Commission's rules and regulations set forth in 10 CFR Chapter I; The facility will operate i'n conformity with the application, the provisions of'he Act, and the rules and regulations of the Commi ssion; There is treasonable 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; 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 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 Provisional Operating License No.
DPR-18 is hereby amended to read as follows:
(2)
Technical S ecifications The Technical Specifications contained 'in Appendix A, as revised through Amendment No. 29, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the, date of its issuance.
R.THE NUCLEAR REGULATORY COMMISSION Dennis L. Ziemann, ief Operating Reactors Branch 82 Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Date of Issuance:
August 24, 1979
ATTACHMENT TO LICENSE AMENDMENT NO. 29 PROVISIONAL OPERATING.LICENSE NO.
DPR-18 DOCKET NO. 50-244 Change the Technical Specifications contained in Appendix A of License No.
DPR-18 as indicated below.
The revised pages contain the captioned amendment number and marginal lines to reflect the area of change.
REMOVE 3.4-1 3.4-2 3.4-3 4.8-1 4.8-2 INSERT
- 3. 4-1 3.4-2 3.4-3 3.4-4 4.8-1 4.8-2 4.8-3
3e4 Turbine C
le
~A1I 1R A lies to the operating status of turbine cycle.
pp es 0
Obiective To define conditions ot the turbine cycle steam-re] ieving capacity.
Auxiliary Feedwater System and Service Mater System operation is necessary to ensure the capabi]ity.
to remove 'decay heat from the core.
The Standby Auxiliary
. Feedwater System provides additional assurance of capa-bility to remove decay heat from the core should the Auxiliary Feedwater System be unavailable.
3.4.1 Mhen the reactor coolant temperature is above 350 F, the following conditions shall be met:
a.
A minimum turbine cycle code approved steam-relieving capability of eight (8) main steam valves available (except for testing of the main steam safety valves).
b.
Three auxiliary feedwater pumps and their associated flow paths (including backup supply from the Service Mater System) must be operable.
c.
A minimum of 15,000 gallons of water shall be available in the condensate storage tanks for the Auxiliary Feedwater System.
d.
Two Standby Auxiliary Feedwater pumps and associated flow path (including flow path from the Service Mater System) must be operable.
3.4-1 Amendment No.
2g
Actions To Se Taken If Conditions of 3.4.1 Are Not Met a ~
With one or more main steam code safety valves inoperable, restore the inoperable valve(s) to operable status within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or, be in at least hot shutdown within the next 6
hours and in cold shutdown within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
b.
c ~
e.
With one auxiliary feed pump inoperable, restore the pump to operable status within 7 days.
If the pump is not restored to operable status within 7 days submit a Thirty Day Mritten Report in accordance with Specification 6.9.2, P
outlining the cause of the inoperability and plans for restoring the pump to operable status.
With two auxiliary feed pumps inoperable, restore two pumps 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 hot shutdown within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> (and in cold shutdown
~~
within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />).
With one standby auxiliary feed pump inoperable, restore two pumps to operable status within 7 days or be in hot shutdown within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and cold shutdown within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
With the required 15,000 gallons of water unavailable to condensate storage tanks, within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, either:
1.
Restore the required amount of water or be in hot shutdown within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, or 2.
Demonstrate the operability of the Service Mater System as a
backup supply to the auxiliary.feed system and restore the required amount of water in the condensate storage tanks within 7 days or be in hot shutdown within the following 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
- 3. 4-2 Amendment No. 2g
Basis:
A reactor shutdown from power requires removal of core decay heat.
Immediate decay heat removal requirements are normally satisfied by the steam bypass to the condenser.
Therefore, core decay heat can be continuously dissipated via the steam bypass to the condenser as feedwater in the steam generator is converted to steam by heat absorption.
Normally, the capability to return feedwater flow to the steam generators is provided by operation of the turbine cycle feedwater system.
Th'e eight main steam safety valves have a total combined rated capability of 6,580,000 lbs/hr.
This capability exceeds the total full power steam flow of 6,577,279 lbs/hr.
In the event of complete loss of off-site electrical power to the station, decay heat removal is assured by either the steam-driven auxiliary feedwater pump or one of the two motor-driven auxiliary feedwater
- pumps, and steam discharge to the atmosphere via the main steam safety valves or atmospheric relief valves.
The turbine driven pump can (1)(2) supply 2005 of the required feedwater and one motor -driven auxiliary feed-water pump can supply 100Ã of the required feedwater for removal of decay heat from the plant, so any combination of two pumps can remove decay heat with a postulated single failure of one pump.
The minimum amount of water in the condensate storage tanks is the amount needed to remove core residual
. and decay heat for 1/2 hour after reactor scram from full power,.
If the
'utage is more than 1/2 hour, Lake Ontario water will be used.
An unlimited supply is available from the lake via either leg of the plant service water system for an indefinite time period.
Amendment No.
29
The Standby Auxiliary Feedwater System is provided to give additional assurance of ihe capability to remove decay heat from the reactor.
The I
system would be used only if none of the auxiliary feedwater pumps were available to perform their intended function.'ince operability require-ments are established for the auxiliary feedwater
- system, the Standby System woul-d be required only if some unlikely event should disable all auxiliary feedwater pumps.
The specified time to restore the Standby System to full capabil'ity is longer than for. other components since the probability of being required to use the'tandby System is extremely low. (3)
References:
(1)
FSAR Section 10.4 (2 )
FSAR Section 14.1. 9 (3)
"Effects of High Energy Pipe Breaks Outside the Containment Building" submitted by letter dated November 1, 1973 from K;
W. Amish, Rochester Gas and Electric Corporation to A. -Giambusso, Deputy Director for Reactor Projects, U. S.
Atomic Energy Commission 3.4-4 Amendment No. 29
4.8 Auxiliar Feedwater S stems A licabilit Applies to periodic testing requirements of the turbine-driven and motor-driven auxiliary feedwater pumps and of the Standby Auxiliary Feedwater pumps.
~0b'ective To verify the operability of the, auxiliary feedwater system and the 'Standby Auxiliary Feedwater System and their ability to respond properly when required.
S ecification
~
~ <<
4.8.1.
4.8.2 4.8.3 4.8.4 Except during cold or refueling shutdowns each motor driven auxiliary feedwater pump unless it is declared inoperable without testing will be started at intervals not to exceed one month and a flow rate of 200 gpm established.
Except during cold or refueling shutdowns the steam turbine driven auxiliary feedwater pump 'unless it is declared inoperable without testing will be started at intervals not to exceed one month and a flow rate of 400 gpm established.
Except during cold or refueling shutdowns the auxiliary feed-water pumps suction discharge and crossover motor operated valves shall be exercised at intervals not to exceed one month.
Except during cold or refueling shutdowns each Standby Auxiliary Feedwater pump unless it is declared inoperable without testing, will be started at intervals not to exceed one month and a flow rate of 200 gpm established.
Amendment No. 5, 29
4.8.5 4.8.6 4.8.7 Except during cold or refueling shutdowns, the suction, discharge, and cross-over motor operated valves for the Standby Auxiliary Feedwater pumps shall be exercised at intervals not to exceed one month.
These tests shall be considered satisfactory if control board indication and subsequent visual observation of the equipment demonstrate that all components have operated properly.
These tests shall be performed prior to exceeding 5Ã power during a startup if the time since the last test exceeds one month.
At least once per 18 months, control of the standby auxiliary feed system pumps and valves from the control room will be demonstrated.
Basis The monthly testing of the auxiliary feedwater pumps by supplying feedwater to the steam generators will verify their ability to meet design.
The flow rates will be measured at a simulated steam generator pressure of 1100 psia.
The capacity of any one of the three auxiliary feedwater pumps is sufficient to meet decay heat removal requirements.
Proper functioning of the steam turbine admission valve and the feedwater pumps start will demonstrate the integrity of the steam drive pump.
Monthly testing of the Standby Auxiliary Feedwater pumps by supplying water from a condensate supply tank to the steam generators will verify their ability to meet design.
The flow rate will be measured at a simulated steam generator pressure of 1'100 psia.
The Standby Auxiliary Feedwater pumps would be used only if all three auxiliary feedwater pumps were Unavai
. -? ~I'.
One o-.
t.i'",.'::@by pu.;!ps would be sufficient to meet 4.8-2
.Amendment No.
29
decay heat removal requirements.
Proper functioning of the suction valves from the service water system, the discharge valves, and the'crossover valves, will demonstrate their operability.
Verification of correct operation will be made both from instrumentation within the main control room and by direct'visual observation of the pumps.
References:
FSAR - Section 10.4 FSAR - Section 14.1.9 FSAR - Section 14.2.5 "Effects of High Energy Pipe Breaks Outside the Containment Building" submitted by letter dated November 1, 1973 from K.
W. Amish, Rochester Gas and Electric Corporation to A. Giambusso, Deputy Director for Reactor Projects, U.
S. Atomic Energy Commission.
4.8-3 Amendment No. 29 A