ML19320C211
| ML19320C211 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 06/02/1980 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19320C210 | List: |
| References | |
| NUDOCS 8007160425 | |
| Download: ML19320C211 (8) | |
Text
a
$m naco (j
UNITED STATES 8
i NUCLEAR REGULATORY COMMISSION
- E WASHINGTON, D. C. 20555
%,,..... s o
YANKEE ATOMIC ELECTRIC COMPANY DOCKET NO. 50-29 YANKEE NUCLEAR POWER STATION (YANKEE-ROWE)
AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 60 License No. DPR-3 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Yankee Atomic Electric Company (the licensee) dated :lanuary 30,1980 (Proposed Change No.168),
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 Conmission'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.
LQ 9007160 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-3 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 60, 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.
FOR THE NUCLEAR REGUALTORY C0hNISSION f
fk PA Dennis M. Crutchfie d Cfiief' '
Operating Reactors Branch M Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: June 2, 1980
ATTACHMENT TO LICENSE AMENDMENT NO. 60 FACILITY OPERATING LICENSE NO. OPR-3 DOCKET NO. 50-29 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages..The revised pages include the captioned amendment number and contain vertical lines indicating the area of change.
REMOVE INSERT 3/4 4-5 3/4 4-Sa
- 3/4 4-5 3/4 4-Sa 3/4 7-5 3/4 7-6 3/d 7-5 3/4 7-Sa i
- Page 3/4 4-5 is merely included to correct an inadvertent error which occurred during the issuance of Amendment No. 59--the relief valve identified in Sec', ton 3.4.2.b.(Page 3/4 4-Sa is an overleaf).
' Overleaf page 3/4 7-6 is also enclosed for document completeness.
MAIN COOLANT SYSTEM
'AFETY VALVES - SHUTDOWN LIMITING CONDITION FOR OPERATION 3.4.2 At least the following safety and/or relief valves shall be OPERABLE; a.
A minimum of one pressurizer code safety valve shall be OPERABLE with a lift setting of 2485 psig +0, -3% or 2560 psig
+0, -3%.
b.
The Main Coolant System (MCS) pressurizer power operated relief valve (PORV) PR-50V-90 shall be OPERABLE in the low pressure mode whenever MCS temperature is < 324*F.
c.
Shutdown Cooling System (SCS) safety valves SV-204 and SV-205 shall be OPERABLE whenever MCS temperature is < 300 F.
APPLICABILITY: MODES 4 and 5.
ACTION:
a.
With no pressurizer code safety valve OPERABLE, immediately l
suspend all operations involving positive reactivit;, changes and place the Shutdown Cooling System into operation.
b.
With PR-S0V-90 inoperable and MCS temperature between 300 F and 324'F:
1.
Within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, either; a)
Raise the MCS temperature to : 324 F, or b)
Lower the MCS temperature to < 300 F and place the SCS safety valves into operation Sy:
1)
Opening SP-MOV-551, 552, 553 and 554, and 2)
Verifying that the safety valves are lined up to discharge to either the low pressure surge tank (LPST) or the primary drain collecting tank (PDCT),and 2.
Restore PR-SOV-90 to OPERABLE status within 7 days. or.
3.
Within the next 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, depressurize and vent the MCS to the atmosphere, the LPST or the PDCT.
. YANKEE-ROWE 3/4 4-5 Amendment No. E, 60
-(Correction)-
MAIN COOLANT SYSTEM LIMITING CONDITION FOR OPERATION ACTION (Continued)'
c.
With one SCS safety valve or PR-50V-90 inoperable and MCS temperature < 300'F, restore the inoperable valve to OPERABLE status withiii 7 days or depressurize and vent the MCS to the atmosphere, the LPST or the PDCT within the next 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
d.
With more than one pressurizer PORV and/or SCS safety valve inoperable and MCS temperature is < 300*F. depressurize and vent the MCS to the atmosphere, the LPST or the PDCT within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
SURVEILLANCE REOUIREMENTS 4.4.2.1 The pressurizer code safety valve shall be demonstrated OPERABLE l
per Surveillance Requirement 4.4.3.
4.4.2.2 The MCS pressurizer PORV PR-50V-90 low setpoint system shall be demonstrated OPERABLE at least once Der:
a.
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by verifying the low setpoint system keylock switch to be in the armed position, b.
31 days by verifying valve PR-MOV-512 to be e-an and valve PR-V-608 to be locked open.
c.
18 months by performance of a CHANNEL CAllBRATION and verifying that the PORV cpens t.t 500 f,30 psig and closes at 470 + 20 psig.
4.4.2.3 The SCS safety valves shall be demonstrated OPERABLE; a.
At least' once per 31 days by verifying that 1.
Valves SC-MOV-551, 552, S., and 554 are locked open.
2.
Safety valves SV-204 and 205 are lined up to discharge to either the LPST or the PDCT.
b.
Per ASME Section XI, Summer 1975 Addenda with a setpoint of 425 psig 1,3*J.
YANKEE-ROWE 3/4 4-5a Amendment No. 59, 50
.- y
m..
PLANT SYSTEMS EMERGENCY BOILER FEE 0 WATER SYSTEM LIMITING CONDITION FOR OPERATION 3.7.1.2 The emergency boiler feedwater system shall be OPERABLE with the
~ h emergency boiler feedwater pump capable of being powered from an OPERABLE steam supply system.
APPLICABILITY: MODES 1, 2 and 3.
ACTION:
With the emergency boiler feedwater system inoperable, be in at least HOT STANDBY within one hour and 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 />.
,:=...
SURVEILLANCE REOUIRFMENTS
..g=l~
4.7.1.2 The emergency boiler feedwater system shall be demonstrated OPERABLE:
...jip
.:.h$-[
a.
At least once per 15 days by:
1.
Starting the pump,
. ]-
2.
Verifying that, on recirculation flow, the steam turbine driven
- gg
- :=
pump develops a discharge pressure of 1 950 psig when the
=
secondary steam press.ure is greater than 100.psig, 3.
Verifying that the pump operates for at least 15 minutes,
][
4.
Cycling each testable manual valve in the flow path through at
' 55.:.
least one complete cycle of full travel, and
=r-g 5.
Verifying that each valve in the flow path that could
~~~
interrupt all emergency boiler feedwater flow is locked open and the remaining valves are verified to be in g=
the correct positio.1.
b.
At least once per 18 months during shutdown by:
- [.(
1.
Cyclir.g each manual valva in the flow pat'1 that is not testable
_I during plant operation, through at least one complete cycle of
- f.==
full travel.
- . T.ih 2.
Verifying that the steam turbine driven pump develops a discharge 5.l:T~
pressure of > 950 psig at a flow of > 80 gpm while feeding a HETj 2
3.
Cycling each main feed control valve manually through at least one complete cycle of full travel.
' *..,.}..
YANKEE-ROWE 3/4'7-5 Amendment No. 60
==5......
=. =.
PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) c.
Prior to startup from COLD SHUTDOWN by:
1.
Verifying that each valve in the flow path from the emergency boiler feedwater source to the main feedwater 1.ines is properly aligned to provide an uninterrupted 4
flow path to the main feedwater system from the emergency boiler feedwater system, and 2.
Perfoming a flow test from the emergency boiler feedwater source to the steam generator to verify the nonnal flow path.
)
s d
e 6
i YANKEE-ROWE 3/4 7-Sa Amendme,No.60,
~
2
PLANT SYSTEMS PRIMARY AND DEMINERALIZED WATEP. STORAGE TANKS LIMITING CONDITION FOR OPERATIDN 3.7.1.3 The primary (PWST) and demineralized (DWST) water storage tanks shall be OPERABLE with a minimum combined contained volume of 85,000 gallons of water.
APPLICABILITY: MODES 1.,2 and 3.
ACTION:
With the PWST and DWST inoperable, be in at least HOT STANDBY within one hour and 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 />.
SURVEILLANCE REQUIREMENTS 4.7.1.3 The PWST and DWST shall be demonstrated OPERABLE 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 the combined contained water volume is within its limits.
i YANKEE-ROWE 3/4 7-6 l
- -