ML20215C899
| ML20215C899 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 12/04/1986 |
| From: | POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK |
| To: | |
| Shared Package | |
| ML20215C893 | List: |
| References | |
| JPN-86-56, NUDOCS 8612150494 | |
| Download: ML20215C899 (9) | |
Text
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ATTACHMENT I TO JPN 56 i
PROPOSED TECHNICAL SPECIFICATION CHANGES REGARDING HPCI/RCIC OPERABILITY REQUIREMENTS PTS-85-11 8612150494 861204
~~
PDR ADOCK 05000333 P
PDR NEW YORK POWER AUTHORITY JAMES A.
FITZPATRICK NUCLEAR POWER PLANT DOCKET NO. 50-333 DPR - 59
JAFNPP 3.5 (Cont'd) 4.5 (Cont'd)
DELETED C.
HIGH PRESSURE COOLANT INJECTION (HPCI SYSTEM)
C.
HIGH PRESSURE COOLANT INJECTION (HPCI SYSTEM)
Surveillance of HPCI System shall be performed as follows provided a'
reactor steam ' supply' is.
available.
-If steam is not available at the time the surveillance test is scheduled to be performed, the test shall be performed _ within 10 days of continuous operation f rom the time' steam becones available.
1.
The HPCI System shall be operable whenever 1.
HPCI System testing shall be as specified in the reactor pressure is greater than 150 4.5.A.l.a, b,
c, d, f, and g except that the.
g psig and reactor coolant temperature is HPCI pump shall deliver at. least 4,250 gpm l
greater than 212*F and irradiated fuel is in against a system head corresponding to a the reactor
- vessel, except as specified reactor vessel pressure of 1,120 psig to 150 below:
psig.
Amendment [, [
117
JAFNPP 4.5 (cont'd) 3.5 (cont'd) a.
When it is determined that the HPCI subsystem the HPCI System From and after the date that is inoperable the RCIC, the LPCI subsystem, a.
is made or found to be inoperable for any both core spray subsystems, and the ADS reason, continued reactor operation is per-missible only during the succeeding 7 days subsystem actuation logic chall be demonstrated to be operable immediately.
unless such system is sooner made operable, The RCIC system and ADS subsystem logic provided that during such 7 days all active shall be demonstrated to be operable daily components of the Automatic Depressurization thereafter, System, the Core Spray System, LpCI System, and Reactor Core Isolation Cooling System are operable, b.
If the requirements of 3.5.C cannot be met, the reactor shall be placed in the cold condition and pressute less than 150 psig within 24 hrs.
2.
Low power physics testing and reactor operator training shall be permitted with reactor coolant temperature 6 212*F with an inoperable com-l ponent(s) as specified in 3.5.C.1 above.
Amendment No. #
118
JAFNPP 4.5 (Cont'd) 3.5 (Cont'd)
E.
Reactor Core Isolation Cooling (RCIC) System E.
Reactor Core Isolation Cooling (RCIC) System f
i 1.
The RCIC System shall be operable whenever 1.
RCIC System testing shall be ~ performed as there is irradiated fuel in the reactor follows provided a reactor steam supply is vessel and the reactor pressure is greater available.
If steam is not available at the than 150 psig and reactor coolant tempera-time the surveillance test is scheduled to ture is greater than 212*F except from the be performed, the test shall be performed 1
time that the RCIC System is made or found within ten days of continuous operation from to be inoperable for any reason, continued the time steam becomes available.
reactor power operation is permissible during the succeeding 7 days unless the Item Frequency system is made operable earlier provided that during these 7 days the HPCI System is a.
Simulated Once/ operating Automatic cycle operable.
Actuation 2.
If the requi rements of 3.5.E cannot be met, Test the reactor shall be placed in the cold condition and pressure less than 150 psig b.
Pump Operability Once/ month within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
c.
Motor Operated Once/ month 3.
Low power physics testing and reactor opera-Valve Operability tor training shall be permitted with inoper-able components as specified in 3.5.E.2 d.
Flow Rate Once/3 months
- above, provided that reactor coolant e.
Testable Tested for opera-temperature isi 212*F.
Check Valves bility any time the reactor is in the cold condition I
exceeding 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, if operability tests have not been performed during the pre-ceding 31 days.
Amendment J0' i
JAFNPP 3.5 BASES (cont'd)
C.
High Pressure Coolant Injection (HPCI) System enable the Core Spray or LPCI Systems to provide pro-tection against the small pipe break in the event of The High Pressure Coolant Injection System is HPCI failure, by depressurizing the reactor vessel provided to adequately cool the core for all pipe rapidly enough to actuate the Core Spray or LPCI breaks smaller than those for which the LPCI or Systems.
The core spray and/or LPCI prov,ide suffi-Core Spray Systems can protect
'.ie core.
cient flow of coolant to limit fuel clad temperatures to well below clad fragmentation and to assure that The HPCI meets this requirement without the use core geometry remains intact, of a-c electrical power.
For the pipe breaks for which the HPCI is intended to function, the core Redundancy has been provided in the automatic pressure never uncovers and is continuously cooled and relief function in that only six of the seven valves thus no clad damage occurs.
Refer to Section are required to operate.
Loss of one of the relief 6.5.3 of the FSAR.
valves does not materially affect the pressure re-lieving capability, and therefore a thirty-day repair Low power physics testing and reactor operator period is specified.
Loss of more than one relief training with inoperable component (s) will be valve significantly reduces the pressure relief capa-conducted only when the HPCI System is not bility, and thus a 24-hr. repair period is specified, required, (reactor coolant temperaturen 212*F and coolant pressure i 150 psig).
If the plant Low power physics testing and reactor operator paramet'ers are below the point where the HPCI training with inoperable components will be conducted System is required, physics testing and operator only when that component or system is not required, training will not place the plant in an unsafe (reactor coolant temperature 6 212*F and reactor condition.
vessel vented or the reactor vessel head removed).
With the reactor coolant temperature $ 212*F and the Operability of the HPCI System is required only Reactor vessel vented or the when reactor pressure is greater than 150 psig and reactor coolant temperature is greater than 212*F because core spray and low pressure coolant injection can protect the core for any size pipe break at low pressure.
D.
Autcmatic Depressurization System (ADS)
The relief valves of the ADS are a backup to the HPCI subsystem.
They 128
, ~.
JAFNPP 4 -
3.5 BASES (cont'd) vessel head off the LPCI and Core Spray Systems testing and operator training will not place the will perform their designed safety function plant in.an unsafe condition.
withoat the help of the ADS.
Operability of the RCIC System is required only E.
Reactor Core Isolation Cooling (RCIC) System when reactor pressure is greater than 150 psig and reactor coolant temperature is greater than The RCIC is designed to provide makeup to the 212*F because core spray and low pressure coolant Reactor Coolant System as a planned operation for injection can protect the core for any size pipe periods when the normal heat sink is unavailable, break at low pressure.
The RCIC also serves as redundant makeup system on total loss of all offsite power in the event F.
Minimum Emergency Core and Containment Cooling that HPCI is unavailable.
In all other System Availability postulated accidents and transients, the ADS provides redundancy for the HPCI.
Based on this The purpose of Specification 4.5.D is to assure a and judgements on the reliability of the HPCI minimum of emergency core cooling equipment is system, an allowable repair time of 7 days is available at all times.
If, for example, one core specified.
Immediate and daily demonstrations of spray were out of service and, the emergency bus HPCI operability during RCIC outage is considered which powered the opposite core spray were out of adequate based on judgement and practicality, service, only two RHR Pumps would be available.
Likewise, if two RHR pumps were out of service Low power physics testing and reactor operator and two RHR on the opposite side were also out of training with inoperable components will be con-service, no containment cooling would be avail-ducted only when the RCIC System is not required, able.
It is during refueling outages that major l
(reactor coolant temperature 5 212* F and coolant maintenance is performed and during such time l
pressure 6 150 psig).
If the plant parameters that all low pressure core cooling systems may be are below the point where the RCIC System is out of service.
This specification provides that l
required, physics should this occur, no work will be performed on the Reacto Coolant System which could lead to l
l draining the vessel.~ This work would include work on certain control rod drive components and Reactor Recirculation System.
Thus, the specifi-cation precludes the events which could require core cooling.
Specification 3.9 must also be consulted to determine other Amendment No. J4" 129
4 ATTACHMENT II TO JPN-86-56 PROPOSED TECHNICAL SPECIFICATION CHANGES REGARDING HPCI/RCIC OPERABILITY REQUIREMENTS PTS-85-11 I
NEW YORK POWER AUTHORITY JAMES A.
PITZPATRICK NUCLEAR POWER PLANT i
DOCKET NO. 50-333 DPR - 59 i
Section 1 - Description of the Chanasa Th3 propossd changes to the Technical Specifications are shown in Attachment I to the Application for Amendment.
This proposed Amendment revises Sections 3.5.C.1 (page 117) and 3.5.E.1 (page 121) and the Bases on pages 128 and 129.
The changes on these pages would delete the requirement that the High Pressure Coolant Injection (HPCI) and Reactor Core Isolation Cooling (RCIC) Systems be operable prior to reactor startup from a cold condition.
The proposed Amendment also include an administrative change on page 118, which revises the cross reference contained within Section 3.5.C.2 to correctly state,
"....as specified in 3.5.C.1 above.".
Section II - Purpose of the Chances The proposed changes would delete the requirement that the HPCI and RCIC Systems be operable prior to reactor startup from a cold condition.
This change has been proposed because it is not necessary for the HPCI or RCIC systems to be operable when no steam is available to operate the HPCI or RCIC turbines.
This change would also eliminate an uncouple / couple cycle of the turbine (s) under some circumstances and potentially avoid the associated labor and radiation exposures.
It also allows pressure testing of the reactor vessel since this is done with reactor coolant temperature below 212*F.
l The requirement that the HPCI and RCIC Systems be operable whenever the reactor pressure is greater than 150 psig and reactor coolant temperature is greater than 212*F and irradiated fuel is in the l
reactor vessel ensures that the functions for which the HPCI and l
RCIC Systems were designed will be available when needed.
Because the low-pressure cooling systems (LPCI and core spray) are capable of providing all the cooling required for any plant event when reactor pressure is below 150 psig, the HPCI and RCIC Systems are not required below this pressure.
LPCI and core spray are capable of providing cooling even when reactor pressure is substantially above 200 psig.
Section III - Impact of the Chances The proposed changes do not change any system or subsystem and will not alter the conclusions of either the FSAR or SER accident analyses.
No accident analysis assumes that the HPCI and RCIC systems are operable below 150 psig and below 212*F.
The proposed change does not involve a significant hazards consideration, using the standards in 10 CFR 50.92, because operation of the FitzPatrick Plant in accordance with this change would not:
(1) involve a significant increase in the probability or consequences of an accident previously evaluated.
The current Technical Specification requirement that the HPCI and RCIC Systems be operable whenever the reactor pressure is greater than 150 psig and irradiated fuel is in the reactor vessel would not be affected by this change.
Thic requirement ensures that the functions for which the HPCI and RCIC Systems were designed will be available when needed.
Because the low-
.. pre 3Curo" cooling systets:(LPCI and core spray) are capable of providing all the cooling requirsd for any plant event whsn resctor pressure.is below 150 psig, ths HPCI and RCIC SystcEs are not required below this pressure.
(2) create'the possibility of a new or different kind of accident from any previously analyzed.
Since HPCI and RCIC are not required for cooling for any plant event when reactor pressure is below 150 psig and reactor coolant temperature is below 212*F. the elimination of the requirement that these systems be operable prior to reactor startup does not create the Possibility of a new or different kind of accident not previously analyzed.
The current Technical Specifications permit the HPCI and RCIC Systems to be inoperable below 150 psig as long as they were operable prior to startup.
(3) involve a significant reduction in a margin of safety because the HPCI and RCIC systems are not required for any safety related function when reactor pressure is below 150 psig.
Since the current requirement that these systems be operable whenever reactor pressure is greater than 150 psig is not affected by this change, there is no reduction in any margin of safety.
Section IV - Implementation of the Changes Implementation of the changes, as proposed, will not impact the ALARA or fire protection programs at FitzPatrick, nor will the changes impact the environment.
Section V - Conclusion l
The incorporation of these changes:
a)
Will not change the probability nor the consequences of an accident or malfunction of equipment important to safety as previously evaluated in the Safety Analysis Report; b)
Will not increase the possibility of an accident or malfunction of different type than any evaluated previously in the Safety Analysis Report; c)
Will not reduce the margin of safety as defined in the basis for any Technical Specifications; d) does not constitute an unreviewed safety question as defined in 10 CFR 50.59; and e)
Involves no significant hazards considerations, as defined in 10 CFR 50.92.
Section VI - References 1)
James A. FitzPatrick Nuclear Power Plant Final Safety Analysis Report (FSAR), Rev 2, July 1984, 2)
James A. FitzPatrick Nuclear Power Plant Safety Evaluation Report (SER).
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