ML20212J319
| ML20212J319 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 10/01/1999 |
| From: | Clifford J NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20212J322 | List: |
| References | |
| NUDOCS 9910050113 | |
| Download: ML20212J319 (12) | |
Text
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4 UNITED STATES g
j NUCLEAR REGULATORY COMMISSION WASHINGTON. D.C. 20555 4001 4
o 9.....g VERMONT YANKEE NUCLEAR POWER CORPORATION DOCKET NO. 50-271 VERMONT YANKEE NUCLEAR POWER STATION AMENDMENT TO FACILITY OPEPATING LICENSE Amendment No.177 License No. DPR-28 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment filed by the Vermont Yankee Nuclear Power Corporation (the licensee) dated July 20,1999, as supplemented by letter dated August 17,1999, 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 app;ication, 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; l
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.
9910050113 991001 PDR ADOCK 05000271 P
e.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.B of Facility Operating License No. DPR-28 is hereby amended to read as follows:
(B) Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No.177, 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 its date of issuance and shall be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION ld.
J.mes W. Clifford, Chief, Section 2 Project Directorate l Division of Licensing Project Management j
Office of Nuclear Reactor Regulation j
Attachment:
Changes to the Technical Specifications Date of issuance: October 1,1999 i
ATTACHMENT TO LICENSE AMENDMENT NO.177 FACILITY OPERATING LICENSE NO. DPR-23.
1 DOCKET NO. 50-271 Replace the foUowing 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.
l Remove Insert I
s105 105 106 106
'107 107
)
108 108 111a-111a 112 112 113 113 114 114 120 120 l
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VYNPS 3.5 LIMITING CCNDITION FOR 4.5 SURVEILLANCE REQUIREMENT OPERATION 3.
From and after the date 3.
When the Alternate that the Alternate Cooling Tower System is Cooling Tower System is made or found to be made or found to be inoperable, all active inoperable for any components of the Station reason, reactor operation Service Water System and is permissible only both essential equipment
'during the succeeding cooling loops shall have seven days, unless the been or shall be Alternate Cooling Tower demonstrated to be J
System is made operable, operable within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
provided that during such seven days all active components of the Station Service Water System and both essential equipment cooling loops are operable.
4.
If the requirements of Specification 3.5.D i
cannot be met, an orderly shutdown shall be initiated and the reactor shall be in a cold shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
E.
High Pressure Cooling E.
High Pressure Coolant Injection (HPCI) System Injection (HPCI) System Surveillance of HPCI System shall be performed as follows:
1.
Except as specified in
- 1. Testing Specification 3.5.E.2, whenever irradiated fue]
- a. A simulated automatic is in the reactor vessel actuation test of the and reactor steam HPCI System shall be pressure is greater than performed during each 150 psig:
refueling outage, a..
The HPCI System
- b. Operability testing of shall be operable, the pump and valves shall be in *ccordance b.
The condensate with Specification storage tank shall 4.6.E.
contain at least 75,000 gallons of
- c. Upon reactor startup, condensate water.
HPCI operability testing shall be performed as required by Specification 4.6.E within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after exceeding 150 psig rer.ctor steam pressure.
Amendment No. E 444, W, M4, m, 177 105
n, VYNFS 3.5 LIMITING CONDITION FOR 4.5 SURVEILLANCE REQUIREMENT i
OPERATION 2.
From and after the date
- d. The HPCI System shall that tne HPCI Subsystem deliver at least 4250 is made or found to be gpm at normal reactor inoperable for any cperating pressure when reason, reactor operation recirculating to the is permissible only Condensate Storage during the succeeding
- Tank, seven days unless such subsystem is sooner made 2.
When the HPCI Subsystem operable, provided that is made or found to be during such seven days inoperable, the Automatic all active components of Depressurization System the Automatic shall have been or shall Depressurization be demonstrated to be Subsystems, the Core operable within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Spray Subsystems, the LPCI Subsystems, and the N0'E: Automatic RCIC System are operaale.
Depressurization
/
3.
If the requirements of System operability shall be either Specification 3.5.E or Specification demonstrated by performing a 4.5.E.1.c cannot be met, functional test of an orderly shutdown shall be initiated and the the trip system
- logic, reactor pressere shall be reduced to 5 150 psig within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
F.
Automatic Deoressuri:ation F.
Automatic Deeressurization System System
{
i Surveillance of the Automatic Depressurization System shall be performed as follows:
1.
.Except as specified in l
Specification 3.5.F.2 1.
Operability testing of
{
below, the entire the relief valves shall
(
Automatic be in accordance with j
Depressurization Relief Specification 4.6 E.
l System shall be operable at any time the reactor steam pressure is above 150 psig and irradiated d
fuel is in the reactor i
vessel.
2.
From and after the date 2.
When one relief valve of that one of the four the Automatic Pressure relief valves of the Relief Subsystem is made Automatic or found to be Depressurization inoperable, the HPCI J
Subsystem are made or Subsystem shall have been found to be inoperable or shall be demonstrated due to malfunction of the to be operable within electrical portion of the 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
valve when the Amendment No. G4, 444, 444, 444, 177 106
VTIPS 3.5 LIMITING CCNDITION FCR 4.5 SURVEILLANCE REQUIREMENT OPERATION reactor is pressurized above 150 psig with irradiated fuel in the reactor vessel, continued reactor operation is permissible only during the succeeding seven days unless such a valve is i
sooner made operable, provided that during such seven days both the remaining Automatic Relief System valves and the HPCI System are operable.
3.
If the requirements of Specification 3.5.F cannot be met, an orderly shutdown shall be initiated and the reactor pressure shall be reduced to 5 150 psig within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, i
G.
Reactor Core Isolation G.
Reactor Core Isolation Cooling System (RCIC)
Cooling System (RCIC) j Surveillance of the RCIC System shall be performed as follows:
1.
Except as specified in
- 1. Testing Specification 3.5.G.2 below, the RCIC System
- a. A simulated automatic shall be operable actuation test (testing whenever the reactor valve operability) of steam pressure is greater the RCIC System shall than 150 psig and be performed during irradiated fuel is in the each refueling outage.
r,eactor vessel.
- b. Operability testing of 2.
From and after the date the pump and valves that the RCIC System is shall be in accordance made or found to be with Spccification inoperable for any 4.6.E.
reason, reactor operation is permissible only
- c. Upon reactor startup, during the succeeding RCIC operability 7 days unless such system testing shall be is sooner made operable, performed as required provided that during such by Specification 4.6.E 7 days all active within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after components of the HPCI exceeding 150 psig System are operable.
reactor steam pressure.
Amendment No. H, M, M4, Me, M4, 177 107
IL VYN'S 3.5 LIMITING CCNDITION FOR 4.5 SURVElLLANCE REQUIREMENT OPERATICN 3.
If the requirements of
- d. The RCIC System shall either Specification deliver at least 400 3.5.G or Specification gpm at normal reactor 4.5.G.1.c cannot be met, operating pressure when an orderly shutdown shall tecirculating to the be initiated and the Condensate Storage reactor pressure shall be Tank.
l reduced to s 150 psig within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
H.
Minimum Core and Containment H.
Minimum Core and Containment Cooling System Availability Cooling System Availability e
1.
During any period when 1.
When one of the emergency one of the emergency diesel generators is made diesel generators is or found to be incperable, continued inoperable, the remaining reactor operation is diesel generator shall permissible only during have been or shall be the succeeding seven demonstrated to be days, provided that all operable within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
of the LPCI, Core Spray and Containment Cooling Subsystems connecting to the operable diesel generator shall be operable.
If this requirement cannot be met, an orderly 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 />.
2.
Any ecmbination of inoperable components in the Core and Containment Cooling Systems shall not defeat the capability of the remaining operable components to fulfill the core and containment cooling functions.
3.
When irradiated fuel is in the reactor vessel and the reactor is in the cold shutdown condition, all Core and Containment Cooling Subsystems may be inoperable provided no work is permitted which has the potential for draining the reactor j
i vessel.
Amendment No. 44, 444, 444, 177 108
" ~,
~
BASES:
3.5 (Cont'd)
SSW pump, SSW valve, etc.), then reactor cperation is limited to 15 days provided that during this time both the normal and emergency pcwer supplies for the remaining operable equipment are also operable, in addition to demonstrating the operability of all remaining active ecmponents of the SSW system which perform a safety function and the alternate cooling tower fan.
If the SSW System would not be capable of performing its safety function for any reason, even without assuming a worst case single active failure, then the reactor must be placed 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 />.
E.
High Pressure Coolant Injection System The High Pressure Coolant Injection System (HPCIs) is provided to adequately cool the core for all pipe breaks smaller than those for which the LPCI or Core Spray Cooling Subsystems can protect the core.
The HPCIs meets this requirement without the use of outside power.
For the pipe breaks for which the HPCIs is intended to function the core never uncovers and is continuously cooled; thus, no clad damage occurs and clad temperatures remain near normal throughout the transient.
J
Reference:
Subsection 6.5.2.2 of the FSAR.
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F.
Automatic Deeressurization System The Automatic Depressurization System (ADS) consists of the four safety-4 relief valves and serves as a backup to the High Pressure Coolant Injection System (HPCI). ADS is designed to provide depressurization of the reactor coolant system during a small break loss-of-coolant accident
{
if HPCI fails or is unable to maintain suf ficient reactor water level.
Since HPCI operability is required above 150 psig, ADS operability is also required above this pressure.
ADS operation reduces the reactor pressure to within the operating pressure range of the low pressure coolant injection and core spray systems, so that these systems can provide reactor coolant inventory makeup.
j G.
Reactor Core Isolation Cooling System The Reactor Core Isolation Cooling System (RCIC) is provided to maintain the water inventory of the reactor vessel in the event of a main steam line isolation and complete loss of outside power without the use of the emergency core cooling systems.
The RC!C meets this requirement.
Reference Section 14.5.4.4 FSAR.
The HPCIS provides an incidental backup to the RCIC system such that in the event the RCIC should be inoperable no loss of function would occur if the HPCIS is operable.
H.
Minimum Core and Containment Cooling System Availability The core cooling and the containment cooling subsystems provide a method of transferring the residual heat following a shutdown or accident to a heat sink.
Based on aralyses, this specification assures that adequate cooling capacity is available by precluding any combination of inoperable components from fulfilling the core and containment cooling function.
It is permissible, based upon the low heat load and other methods available to remove the residual heat, to disable all core and containment cooling systems for maintenance if the reactor is cold and shutdown and there is Amendment No. 44, 444, 449, 177 lila
4 VYNPS BASES:
3.5 (Cont'd) no potential for draining the reactor vessel.
However, if refueling operations are in progress, one coolant injection system, one diesel and a residual of at least 300,000 gallons is required to assure core flooding capability.
I.
Maintenance of Filled Discharge Pipe Full discharge lines are required when the core spray subsystems, HECI and RCIC are required to be operable to preclude the possibility of damage to the discharge piping due to water hammer action upon a pump start.
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Amendment No. 44k. 177 112
?fe 4
VYNPS BASES:
4.5;iCORE AND CONTAINMENT COOLANT SYSTEMS
- A.
. Core-Spray and LPCI'-
During normal plant operation, manual tests of operable pumps and valvesishall l>e conducted in accordance with Specification 4.6.E to demonstrate operability.
JO
-During'each refueling shutdown, tests (as summarized below) shall be conducted..to demonstrate' proper autcmatic operation and system
- performance.
Periodic' testing'as described:in Specification 4.6.E will demonstrate that all components which do not operate during normal conditions will
~
operate properly.if required.
TheLautomatic actuation test will be performed by simulation of high drywell pressure or low-low water level. The starting of the pump and actuation of valves ~will be checked.
The normal power supply will be used during the test. -Testing of the sequencing of the pumps when the diesel generator is the source of power will be checked during the testing of the diesel.
Following the automatic actuation test, the flow' rate will be checked by recirculation to the suppression chamber.
The pump ~and valve operability. checks will be performed by manually starting the pump or/ activating the valve.
For the pumps, the pump motors will be run long enough for them to reach operating
- temperatures.
.B. and C.
" Containment' Spray Cooling Capability and RHR Service Water Systems
.The periodic testing requirements specified in Specifications 4.5.B and C will demonstrate that all components will operate properly if required.. Since this is a manually actuated system, no automatic actuation test is required.
The system will~be activated manually and
.the flow checked by'an indicator.in the control recm.
10nce'every five years air tests will be performed to assure that the containment ^ spray header nozzles are operable.
D.,
E., and F.
Station Service Water and Alternate Coolir.q Tower Systems
.and High Pressure Coolant Iniection and Automatic Depressurization System HPCI system testing demonstrates operational readiness of equipment and detects degradations which may affect reliable operation.
Testing is
-conducted during each reactor startuo if.tirtenance that affects
--operability.was performed on the HPCI system.
Periodic testing is also performed in;accordance with Specification 4.6.E and the inservice testing program.
Sufficient steam flow must be available prior to HPCI testing to avoid inducing.an operational transient when' steam is diverted to the HPCI
. system.
Reactor-startup is allowed prior to performing the required surveillance testing in order to achieve adequate steam pressure and.
flow.' 'However, a 24-hour. limitation is imposed for performing operability testing once reactor steam pressure exceeds 150 psig.
The short: duration before full functional testing is performed is
~
considered acceptable.
? AmendmentL No'. - M, M4/ L Me,177 113
n, VYNPS BASES:
4.5 (Cont'd)
The Automatic Depressurization System is tested during refueling outages to avoid an undesirable blowdown of the Reactor Coolant System.
The HPCI Automatic Actuation Test will be performed by simulation of the accident signal.
The test is normally performed in conjunction with the automatic actuation of all Core Standby Cooling Systems.
G.
Reactor Core Isolation Cooling System The frequency and conditions for testing of the RCIC system are the same as for the HPCI system.
Testing is conducted in accordance with Specification 4.6.E and provides assurance that the system will function as intended.
H.
Minimum Core and Containment Cooling System Availability Assurance that the diesels will perform their intended function is i
obtained by the periodic surveillance test and the results obtained j
from the pump and valve testing performed in accordance with ASME Section XI requirements described in Specification 4. 6 E.
Whenever a diesel is inoperable, the potential for extended operation with two diesels inoperable is reduced by requiring that the redundant diesel be j
tested within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
I.
Maintenance of Filled Discharge Pipe Observation of water flowing from the discharge line high point vent as discussed in Section I assures that the Core Cooling Subsystems will not experience water hammer damage when any of the pumps are started.
Core Spray Subsystems and LPCI Subsystems will also be vented through the discharge line high point vent following a return from an inoperable status to assure that the system is " solid" and ready for operation.
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Amendment No. 48, G3, 444, 4G4,I 5 7 114
r, VYNPS 3.6 LIMITING CONDITIONS FOR 4.6 SURVEILLANCE REQUIREMENTS OPERATION D.
Safety and Relief Valves D.
Safety and Relief Valves
- 1. 'During reactor power 1.
Operability testing of operating conditions and Safety and Relief Valves whenever the reactor shall be in accordance coolant pressure is with Specification 4.6.E.
l greater than.150 psig and The lift point of the i
temperature greater than safety and relief valves 3 5 0* F, both safety valves shall be set as specified and at least three of the in Specification 2.2.B.
four relief valves shall be operable.
2.
If Specification 3.6.D.1 is not met, initiate an orderly shutdown and the reactor coolant pressure l
shall be below 150 psig and 350*F within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
E.
Structural Integrity and Operability Testing E.
Structural Integrity and Operability Testing The structural integrity and the operability of the 1.
Inservice inspection of safety-related systems and safety-related components components shall be shall be performed in maintained at the level accordance with required by the original Section XI of the ASME acceptance standards Boiler and Pressure throughout the life of the Vessel Code and plant.
ap;.licable Addenda as required by 10 CFR 50, Section 50.55a(g), except where specific written relief has been granted by the NRC. Inservice inspection of piping, identified in NRC Generic
{
Letter 88-01, shall be performed in accordance with the staff positions on schedule, methods, and personnel and sample expansion included in the Generic Letter, except that sample selection for the scope of Category A welds may be in accordance with ASME Code Case N-560.
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