ML20072H964
| ML20072H964 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 08/22/1994 |
| From: | Chris Miller Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20072H969 | List: |
| References | |
| NUDOCS 9408260173 | |
| Download: ML20072H964 (10) | |
Text
.-
~
ea 05c p
og y*
.4 UNITED STATES g
g NUCLEAR REGULATORY COMMISSION t
WASHINGTON, D.C. 20555-0001 4
4 BOSTON EDISON COMPANY DOCKET NO. 50-293 PILGRIM NUCLEAR POWER STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.156 License No. DPR-35 1.
The Nuclear Regulatory Commission (the Commission or the NRC) has found that:
A.
The application for amendment filed by the Boston Edison Company (the licensee) dated June 9, 1994, and supplemented August 10, 1994, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations;
)
i B.
The facility will operate in conformity with the application, the provisions of the 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 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.
2.
Accordingly, the license is amended by changes to the Technical. Specifica-tions as indicated in the attachment to this license amendment.
9404N260173 94CH322 PIWt A0()CK 05K>00&FP3 -
P PDR
. 3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION UL v
Charles Miller, Acting Assistant Director for Region I Reactors Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: August 22, 1994 l
i ATTACHMENT TO LICENSE AMENDMENT NO.156 FACILITY OPERATING LICENSE N0. OPR-35 DOCKET NO. 50-293 Replace the following pages of the Appendix A Technical Specifications with the attached pages.
The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.
Remove Insert 107 107 108 108 109 109 111 111 116 116 117 117 118 118
LIMITING CONDITION FOR OPERATION SVRVEILLANCE RE0VIREMENT C.
HPCI System C.
HPCI System 1.
The HPCI system hall be operable 1.
HPCI system testing shall be whenever there is irradiated fuel performed as follows:
in the reactor vessel, reactor pressure is greater than 150 psig,
- a. Simulated Once/ operating and reactor coolant temperature is Automatic cycle greater than 365 F; except as Actuation specified in 3.5.C.2 below.
Test 2.
From and after the date that the
- b. Pump Oper-When tested HPCI system is made or found to be ability as specified inoperable for any eeason, in 3.13 verify continued reactor operation is that the HPCI permissible only during the pump delivers succeeding 14 days unless such l
at least 4250 system is sooner made operable, GPM for a providing that during such 14 l
system head days all active components of the corresponding ADS system, the RCIC system, the to a reactor LPCI system and both core spray pressure of
)
systems are operable.
1000 psig 3.
If the requirements of 3.5.C
- c. Motor Operated As specified cannot be met, an orderly shutdown Valve Oper-in 3.13 shall'be initiated and the reactor ability pressure shall be reduced to or below 150 psig within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
- d. Flow Rate at Once/ operating 150 psig cycle verify that the HPCI pump delivers at least 4250 GPM for a system head corresponding to a reactor pressure of 150 psig The HPCI pump shall deliver at least 4250 gpm for a system head corresponding'to a reactor pressure of 1000 to 150 psig.
381-421-44 -198 -199r-1141-135,149,156 107 Amendment No.
1 1
LIMfTING CONDITION FOR OPERATION SURVEftLANCE RE0VIREMENT
)
3.5.D Reactor Core Isolation Coolim 4.5.D Reactor Core Isolation Coolina i
(RCIC) System (RCIC) System 1.
The RCIC system shall be operable 1.
RCIC system testing shall be l
whenever there is irradiated fuel performed as follows:
in the reactor vessel, reactor pressure is greater than 150 psig,
- a. Simulated Once/ operating and reactor coolant temperature is Automatic cycle greater than 365 F; except as Actuation specified in 3.5.D.2 below.
Test 2.
From and after the da'.' that the
- b. Pump When tested RCICS is made or found to be Operability as specified inoperable for any reason, in 3.13 verify continued reactor power operation that the RCIC is permissible only during the pump delivers succeeding 14 days provided that at least 400 during such 14 days the HPCIS is GPM at a operable.
system head corresponding 3.
If the requirements of 3.5.0 cannot to a reactor be met, an orderly shutdown shall pressure of be initiated and the reactor 1000 psig pressure shall be reduced to or below.150 psig within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />,
- c. Motor As specified Operated in 3.13 Valve
)
Operability
- d. Flow Rate at Once/ operating 150 psig cycle verify that the RCIC pump delivers at least 400 GPM at a system head corresponding to a reactor pressure of 150 psig The RCIC pump shall deliver at least 400 gpm for a system head corresponding to a reactor pressure of 1000 to 150 psig.
42,-1991-114 -135,-149, 156 108 Amendment No.
5
LIMITING CONDITION FOR OPERATION SURVEILLANCE RE0VIREMENT 3.5.E Automatic Deoressurization 4.5.E Automatic Deoressurization System (ADS)
System (ADS) 1.
The Automatic Depressurization 1.
During each operating cycle the Systeai shall be operable following tests shall be whenever there is irradiated performed on the ADS:
fuel in the reactor vessel and i
the reactor pressure is greater
- a. A simulated automatic than 104 psig and prior to a actuation test shall be startup from a Cold Condition, performed prior to startup except as specified in 3.5.E.2 after each refueling outage.
below.
The ADS manual inhibit switch will be included in this 2.
From and after the date that one test.
valve in the Automa'...
Depressurization System is made
- b. With the reactor at pressure, or found to be inoperable for each relief valve shall be any reason, continued reactor manually opened until a operation is permissible only corresponding change in I
during the succeeding 14 days reactor pressure'or main unless such valve is sooner made turbine bypass valve operable, provided that during positions indicate that steam l
such 14 days the HPCI system is is flowing from the valve.
3.
If the requirements of 3.5.E cannot be met, an orderly shutdown shall be initiated and the reactor pressure shall be reduced to at least 104 psig within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Amendment No.- 22, 42, 106, 109, 114, } & 156 109
L IMITfNG CONDITION FOR OPERATTON SVRVEILLANCE RE0VIREMENT
~
3.5.F Minimum Low Pressure Coolino and Diesel Generator Availability a) No work en the reactor vessel, in addition to 1
CRD removal, will be performed which has the potential for exceededing the maximum leak rate from a single control blade seal if it became unseated.
b) i) the core. pray systems are operable and aligned with a suction path from the condensate storage tanks.
ii) the condensate storage tanks shall contain at least 200,000 gallons of usable water and the refueling cavity and dryer / separator pool shall be flooded to a i
least elevation 114'-0" i
3.5.G 4
(Intentionally left blank) 3.5.H Maintenance of Filled 4.5.H Maintenance of Filled l
Discharae Pioe Discharae Pioe Whenever core spray systems, LPCI The following surveillance system, HPCI or RCIC are required to requirements shall be adhered to be operable, the discharge piping assure that the discharge piping of from the pump discharge of these the core spray systems, LPCI system, systems to the last block valve HPCI and RCIC are filled:
shall be filled.
1.
Every month the LPCI system and l
core spray system discharge piping shall be vented from the i
high point and water flow I
observed.
i 2.
Following any period where the LPCI system or core spray systems have not been required to be operable, the discharge piping of the inoperable system shall be vented from the high point prior to the return-of the system to service.
Amendment No. 39, F&&,156 111
BASES:
l 3.5.CliPM The limiting conditions for operating the HPCI System are derived from the Station Nuclear Safety Operational Analysis (FSAR Appendix G) and a detailed functional analysis of the HPCI System (FSAR Section 6).
The HPCIS is provided to assure that the reactor core is adequately cooled to limit fuel clad temperature in the event of a small break in the nuclear system and loss-of-coolant which does not result in rapid hpressurization of the reactor vessel.
The HPCIS permits the reactor to be shut down while maintaining sufficient reactor vessel water level inventory until the vessel is depressurized.
The HPCIS continues to operate until reactor vessel pressure is below the pressure at which LPCI operation or Core Spray System operation maintains cor;,.coling.
The capacity of the system is selected to provide this required core cooling.
The HPCI pump is designed to pump 4250 gpm at reactor pressures between 1100 and 150 psig.
Two sources of water are available.
Initially, demineralized water from the condensate storage tank is used instead of injecting water from the suppression pool into the reactor.
When the HPCI System begins operation, the reactor depressurizes more rapidly than would occur if HPCI was not initiated due to the condensation of steam by the cold fluid pumped into the reactor vessel by the HPCI System. As the reactor vessel pressure continues to decrease, the HPCI flow momentarily reached equilibrium with the flow through the break.
Continued depressur'ization causes the break flow to decrease below the HPCI flow and the liquid inventory begins to rise.
This type of response is typical of the small breaks. The core never uncovers and is continuously cooled throughout the transient so that no core damage of any kind occurs for breaks that lie within the capacity range of the HPCI.
The analysis in FSAR Appendix G shows that the ADS provides a single failure proof path for depressurization for postulated transients and accidents.
The RCIC is required as an alternate source of makeup to the HPCI only in the case of loss of all offset A-C power.
Considering the HPCI and the ADS plus RCIC as redundant paths, and considering judgments of the reliability of the ADS and RCIC systems, a 14-day allowable repair time is specified.
l The requirement that HPCI be operable when reactor coolant temperature is greater that 365 F is included in Specification 3.5.C.1 to clarify that HPCI need not be operable during certain testing (e.g., reactor vessel hydro testing at high reactor pressure and low reactor coolant temperature). 365*F is approximately equal to the saturation steam temperature at 150 psig.
l Amendment No. 4 0, 156 116 I
l 1
e BASES:
3.5.D RCIC System The RCIC is designed to provide makeup coolant to the nuclear system as part of the planned operation for periods when the normal heat sink is unavailable.
The Station Nuclear Safety Operational Analysis, FSAR Appendix G, shows that RCIC also serves as redundant makeup system on total loss of all offset power in the event that HPCI is unavailable.
In all other postulated accidents and transients, the ADS provides redundancy for the HPCI.
Based on this and judgments on the reliability of the HPCI system, an allowable repair time of 14 days is specified.
l The requirement that RCIC be operable when reactor coolant temperature is greater than 365 F is included in Specification 3.5.D.1 to clarify that RCIC need not be operable du..ng certain testing (e.g., reactor vessel hydro testing at high reactor pressure and low reactor coolant temperature).
365 F is approximately equal to the saturation steam temperature at 150 psig.
Amendment No. 109,135, k&4,156 117
i
~'
BASES:
3.5.E Automatic Deoressurization System ',405)
The limiting conditions for operating the ADS are derived from the Station Nuclear Safety Operational Analysis (FSAR Appendix G) and a detailed functional analysis of the ADS (FSAR Section 6).
j This specification ensures the operability of the ADS under all conditions for which the automatic or manual depressurization of the nuclear system is an es::ential response to station abnormalities.
]
The nuclear system pressure relief system provides automatic nuclear system depressurization for small breaks in the nuclear system so that the low l
pressure coolant injection (LPCI) and the core spray systems can operate to protect the fuel barrie.
Because the Automatic Depressurization System does not provide makeup to the reactor primary vessel, no credit is taken for the steam cooling of the core caused by the system actuation to provide further conservatism to the CSCS.
Performance analysis of the Automatic Depressurization System is considered i
only with respect to its depressurizing effect in conjunction with LPCI or j
There are four valves provided and each has a capacity of 800,000 j
lb/hr at a reactor pressure of 1125 psig.
i The allowable out of service time for one ADS valve is determined as 14 days l
because of the redundancy and because of HPCIS operability; therefore, redundant protection for the core with a small break in the nuclear system is still available.
The ADS test circuit permits continued surveillance on the operable relief valves to assure that they will be available if required.
1 i
Amendment No. 15, 135, 144, 156 118