ML20116P145
| ML20116P145 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 08/16/1996 |
| From: | Jeffrey Mitchell NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20116P148 | List: |
| References | |
| NUDOCS 9608230162 | |
| Download: ML20116P145 (25) | |
Text
C Clow k
- p UNITED STATES s
j NUCLEAR REGULATORY COMMISSION 2
WASHINGTON, D.C. 206 6 0001 Y+9
,o POWER AUTHORITY OF THE STATE OF NEW YORK DOCKET NO. 50-333 JAMES A. FITZPATRICK NUCLEAR POWER PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.232 License No. DPR-59 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The applications for amendment by Power Authority of the State of New York (the licensee) dated June 15, September 15, October 25, and November 30, 1995, 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; 8.
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 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 regiirements 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 Facility Operating License No. DPR-59 is hereby amended to read as follows:
9608230162 960816 PDR ADOCK 05000333 P
+
. (2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.232, are hereby incorporated in the i
i license. The licensee shall operate the facility in accordance with l
the Technical Specifications, l
3.
This license amendment is effective as of the date of its issuance to be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION g&t ic Jocelyn A. Mitchell, Acting Director Project Directorate I-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications l
Date of Issuance: August 16, 1996 4
l i
l
l-ATTACHMENT TO LICENSE AMENDMENT NO.
FACILITY OPERATING LICENSE NO. OPR-59 DOCKET NO. 50-333 Revise Appendix A as follows:
l Remove Paagi Insert Paaes 88 88 96 96 105 105 l
106 106 107 107 4
109 109
)
i 109a 109a 165 165 178 178 179 179 l
181 181 l
182 182 183 183 f
185 185 195 195 196 196 l
197 197 217 217 222 222 l
222a 222a 222b 222b l
226 226 J
'i l
f JAFNPP 3.3 LIMITING CONDITION FOR OPERATION 4.3 SURVEILLANCE REQUIREMENT 3.3 REACTIVITY CONTROL 4.3 REACTIVITY CONTROL l
l Anchcabahtv:
Anoimatuhtv:
Applies to the operational status of the Control Rod System.
Applies to the surveillance requirements of the Control Rod System.
f Obiective:
Objective:
[
To assure the ability of the Control Rod System to control reactivity.
To verify the ability of the Control Rod System to control reactivity.
i Specification:
Specifmation:
A.
Reactivity Limitations A. Reactivity Limitatsons 1.
Reactivity margin - core loading 1.
Reactivity margin - core loading A sufficient number of control rods shall be operable so Sufficient control rods shall be withdrawn following a that the core could be made subcritical in the most refueling outage when core alterations were performed to reactive conditions during the operating cycle with the demonstrate with a margin of 0.38 percent Ak/k the core strongest control rod fully withdrawn and all other can be made subcritical at any time in the subsequent fuel operable control rods fully inserted.
cycle with the analytically determined strongest control l
rod fully withdrawn and all other operable rods fully inserted.
P i
Amendment No. %6-232 r
88
. - - -.. -~
f JAFNPP t
r i
3.3.C (cont'd) 4.3.C (cont'd) i 2.
The average of the scram insertion times for the three 2.
At 16-week intervals,10 percent of the operable control fastest operable control rods of all groups of four control rod drives shall be scram timed above 950 poig. The same rods in a two-by-two array shall be no greater than:
control rod drives sho.sid not be tested each interval.
Whenever such scram time measurements are made, an 1
Control Rod Average Scram evaluation shall be made to provide reasonable assurance Notch Position Insertion Time that proper control rod drive performance is being Observed (Seconds) maintained.
46 0.361 38 0.977 24 2.112 04 3.764 3.
The maxim *2m scram insertion time for 90 percent 3.
All control rods shall be deturswned operable once every insertion of any operable control rod shalt not exceed 24 :r.orat.s by demonstrating the scram discharge volume 7.00 sec.
drain and vont valves ope *rable when the scram test initiated by placing the mode switch in the SHUTDOWN position is performed as required by Table 4.1-1 and by verifying that the drain and vont valves:
a.
Close in less than 30 seconds after receipt of a signal for control rods to scram, and b.
Open when the scram signal is reset.
Amendment No. 19, S2, 75, SS,155, 203, 232 96
JAFNPP 3.4 LIMITING CONDITIONS FOR OPERATION 4.4 SURVEILLANCE REQUIREMENTS 3.4 STANDBY LlOUlD CONTROL SYSTEM 4.4 STANDBY LIQUID CONTROL SYSTEM Apolicability:
Anolicability:
Applies to the operating status of the Standby Liquid Control Applies to the periodic testing requirements for the Standby Liquid System.
Control System.
Obiective:
Obiective To assure the availability of a system with the capability to shut To verify the operabil;ty of the Standby Liquid Control System.
down the reactor and maintain the shutdown condition without control rods.
Specification:
Soecifications A.
Normal Operation A.
Normal Operation The operability of the Standby Liquid Control System During periods when fuel is in the reactor and prior to shall be verified by performance of the following tests:
startup from a cold condition, the Standby Liquid Control System shall be operable except as specified in 3.4.B 1.
At least once per month -
below. This system need not be operable when the reactor is in the cold condition, all rods are fully inserted Demineralized water shall be recycled to the test and Specification 3.3.A is met.
tank. Pump minimum flow rate of 50 gpm shall be verified against a system head of 2:1,275 psig.
2.
Once oer 24 months -
Manually initiate the system, except the explosive valves. Pump solution through the recirculation path.
Amendment No. 444, 232 105
JAFNPP 4.4 (cont'd)
Explode one of three primer assemblies manufactured in the same batch to verify proper function. Then install the two remaeneng pnmer assemblies of the same batch in the explosive valves.
Demineralized water shall be injected into the reactor vessel to test that valves (except explosive valves) not checked by the recirculation test are not clogged.
Test that the setting of the system pressure relief valves is between 1,400 and 1,490 psig.
3.
Once per 24 months -
Disassemble and inspect one explosive valve so that it can be established that the valve is not clogged.
Both valves shall be inspected within two test intervals.
B.
Operation with inoperable Comoonents B.
Operation with inonerable Components From and after the date that a redundant component is made When a component becomes inoperable its redundant or found to be inoperable, Specification 3.4.A shall be component shall be verified to be operable immediately considered fulfilled, and continued operation permitted, and daily thereafter.
provided that:
1.
The component is retumed to an operable condition within 7 days.
Amendment No. 38,131,'18,232 106 s
b
___,___.______s--
- - = - - - - - - -
~
JAFNPP 3.4 (cont'd)
~
4.4 (cont'd)
C.
Sodium Pentaborate Solution C.
Sodium Pentaborate Solution The standby liquid control solution tank shall contain a boron The availability of the proper boron bearing solution shall be bearing solution with a minimum enrichment of 34.7 atom verified by performance of the following tests:
percent of B-10 that satisfies the volume-concentration requirements of Fig. 3.4-1 at all times when the Standtiy 1.
At least once oer month -
Liquid Control System is required to be operable and the solution temperature including that in the pump suction piping Boron concentration shall be determined. In addition, the shall not be less than the temperature presented in Fig. 3.4-2.
boron concentration shall be determined any time water Tank heater and the heat tracing system shall be operable or enriched codium pentaborate is added or if the solution whenever the SLCS is required in order to maintain solution temperature drops below the limits specified by Figure temperature in accordance with Fig. 3.4-2. If these 3.4-2.
requirements are not met, restore the system to the above limits within eight hours or take action in accordance with 2.
At least once oer day -
Specification 3.4.D.
Solution volume and the solution temperature shall be checked.
3.
At least once oer 18 months -
The temperature and level elements shall be calibrated.
4.
Once per 24 months -
Enrichment of B-10 (in atom percent) shall be checked.
D.
If specifications 3.4.A through C are not met, the reactor shall D.
Not Used be in at least 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 />.
Amendment No.
- 1S,192, 232 107
JAFNPP ATWS requirements are satisfied at all concentrations above The relief valves in the Standby Liquid Control System protect 10 weight percent for a minimum enrichment of 34.7 atom the system piping and positive displacement pumps, which are percent of B-10.
nominally designed for 1,500 psig, from overpressure. The pressure relief valves discharge back to the standby liquid Figure 3.4-1 shows the permissible region of operation on a control pump suction line.
sodium pentaborate solution volume versus concentration graph. This curve was developed for 34.7% enriched B-10' B.
Operation with inoperable Components and a pumping rate of 50 gpm. Each point on this curve provides a minimum of 660 ppm of equivalent natural boron in Only one of two standby liquid control pumping circuits is the reactor vessel upon injection of SLC solution. At a needed for operation..lf one circuit is inoperable, there is no solution volume of 2200 gallons, a weight concentration of immediate threat to shutdown capability, and reactor operation 13% sodium pentaborate, enriched to 34.7% boron-10 is may continue dor:ng repairs. Assurance that the remaining needed to meet shutdown requirements. The maximum system will perform its function is obtained by verifying pump storage volume of the solution is 4780 gallons which is the operability in the operable circuit at least daily.
net overflow volume in the SLC tank.
C.
Sodium Pentaborate Solution Boron concentration, isotopic enrichment of boron-10, solution temperature, and volume are checked on a frequency adequate To guard against precipitation, the solution, including that in to assure a high reliability of operation of the system should it the pump suction piping, is kept at least 10*F above ever be required. Experience with pump operability indicates saturation temperature. Figure 3.4-2 shows the saturation that monthly testing is adequate to detect if failures have -
temperature including 10*F margin as a function of sodium occurred.
pentaborate solution concentration. Tank heater and heat tracing system are provided to assure compliance with this The only practical time to test the Standby Liquid Control requirement. The set points for the automatic actuation of the System is during a refueling outage and by initiation from local tank heater and heat tracing system are established based on stations. Because components of the system are checked the solution concentration. Temperature and liquid level periodically as described above, a functional test of the entire alarms for the system annunciate in the control room. Pump system on a frequency of more than once every 24 months is operability is checked on a frequency to assure a high unnecessary. A test of explosive charges from one reliability of operation of the system should it ever be required.
manufacturing batch is made to assure that the charges are satisfactory. A continuous check of the firing circuit continuity is provided by pilot lights in the control room.
Amendment No. GS, ' 16,'18, 232 109
JAFNPP Once the solution is prepared, boron concentration does not vary unless more enriched sodium pentaborate or more water is added. Levelindications and alarms indicate whether the solution volume has changed which might indicate a possible solution concentration change. The test interval has been established considering these factors.
Boron enrichment (B-10 atom percent) does not vary,with the addition of enriched sodium pentaborate material or water to the SLC tank provided 34.7% enriched (B-10 I
atom percent) is added. Therefore, a check once every 24 months is adequate to ensure proper enrichment.
\\
Artiesidatient No. 44 6,232 109a 4
JAFNPP 3.7 LIMITING CONDITIONS FOR OPERATION 4.7 SURVEILLANCE REQUIREMENTS 3.7 CONTAINMENT SYSTEMS 4.7 CONTAINMENT SYSTEMS Acolicability:
Acolicabihtv:
Applies to the operating status of the primary and secondary Applies to the primary and secondary containment integrity.
containment systems.
Obiective:
Obiective:
To assure the integrity of the primary and secondary containment To verify the integrity of the primary and secondary contaenment systems.
systems.
Specification:
Sancification:
A.
The level from the bottom of the torus and temperature 1.
The torus water level and temperature shall be monitored of the water in the torus shall be maintained within the as specified in Table 4.2-8.
following limits whenever the reactor is critical or whenever the reactor coolant temperature is greater thaan The accessible interior surfaces of the drywell and above 212*F and irradiated fuel is in the reactor vessel:
the water 14*ai of the torus shall be inspected once per 24 months for evidence of deterioration.
a.
Maximum level of 14.00 feet.
Whenever there is indication of relief valve operation or b.
Mmemum level of 13.88 feet.
testing which adds heat to the suppression pool, the pool temperature shall be continuously recorded until the heat The torus water level may be outside the above addition is termeneted. The operator will verify that limits for a maxemum of four (4) hours as a result of average temperature is within applicable limits every 5 required operability testing of HPCI, RCIC, RHR, CS, minutes. In lieu of continuous recording, the operator and the Drywell-Torus Vacuum Relief System.
shalllog the temperature every 5 minutes.
c.
Maximum water temperature Whenever there is indication of relief valve operation with the temperature of the suppression pool reaching 160*F (1) During normal power operation maximum or more and the primary coolant system pressure greater water temperature shall be 95*F.
than 200 psig, an extemal visual examination of the torus shall be conducted before resuming power operation.
Amendment No. 15, OS, iS 150,181, IS" 197,232 165-A
____._,_.__. _.. _.. ~ _ _. _.. _ - - _ _. _ _ _ _ _. _ _ _. _ - - _... _....
t JAFNPP i
i 3.7 (cont'd) 4.7 (cont'd) breaker is sooner made operable, provided that the repair procedure does not violate primary containment integrity.
5.
Pressure Suppression Chamber - Drywell Vacuum 5.
Pressure Suppression Chamber - Drywell Vacuum Breakers Breakers i
a.
When primary containment integrity is required, all a.
Each drywell suppression chamber vacuum breaker drywell suppression chamber vacuum breakers shall shall be exercised through an opening - closang cycle be operable and positioned in the fully closed montisy.
position except during testing and as specified in i
3.7.A.5.b below.
b.
One drywell suppression chamber vacuum breaker b.
When it is determined that one vacuum breaker is may be non-fully closed so long as it is determined inoperable for fully closing when operability is to be not more than 1
- open as indicated by the required, the operable breakers shall be exercir,ed position lights.
immediately, and every 15 days thereafter until the inoperable valve has been returned to normal service.
c.
One drywell suppression chamber vacuum breaker c.
Once per 24 months, each vacuum breeker valve
[;
may be determined to be inoperable for opening.
shall be visually inspected to insure proper maintenance and operation.
d.
Deleted d.
A leak test of the drywell to suppression chamber structure shall be conducted once per 24 months; the acceptable leek rate is 50.25 in, waterknin, over a 10 min period, with the drywell at 1 paid.
i Amendment No. 121,192,232 178 4
JAFNPP 3.7 (cont'd) 4.7 (cont'd) e.
Leakage between the drywell and suppression e.
Not applicable chamber shall not exceed a rate of 71 scfm as monitored via the suppression chamber 10 min pressure transient of 0.25 in. water / min.
f.
The self actuated vacuum breakers shall ope,n f.
Not applicable when subjected to a force equivalent to 0.5 psid acting on the valve disc.
g.
From and after the date that one of the pressure g.
Once per 24 months, each vacuum breaker shall be suppression chamber /drywell vacuum breakers is tested to determine that the force required to open made or found to be inoperable for any reason, the the vacuum breaker does not exceed the force vacuum breaker shall be locked closed and reactor specified in Specification 3.7.A.S.f and each vacuum operation is permissible only during the succeeding breaker shall be inspected and verified to meet seven days unless such vacuum breaker is sooner design requirements.
made operable, provided that the repair procedura does not violate primary containment integrity.
Amendment No. 3, 131,232 179-M P
JAFNPP 3.7 (cont'd) 4.7 (cont'd)
B.
Standbv Gas Treatment System B. Standbv Gas Treatment System 1.
Except as specified in 3.7.B.2 below both circuits of the 1.
Standby Gas Treatment System surveillance shall be Standby Gas Treatment System shall be operable at all performed as indicated below:
times when secondary containment integrity is required.
a.
Once per 24 months, it shall be demonstrated that:
(1)
Pressure drop across the combined high-efficiency and charcoal filters is less than 5.7 in. of water at 6,000 scfm, and (2)
Each 39kW heater shall dissipate greater than 29kW of electric power as calculated by the following expression:
P = /5EI where:
P= Dissipated Electrical Power; E = Measured line-to-line voltage in volts (RMS);
!= Average measured phase current in amperes (RMS).
Amendment No. 10, 2S, OS, SS, 00, 31, 33,131, aa4.,232 181 e
JAFNPP i
f 4.7 (cont'd) b.
At least once during each scheduled secondary I
containment leak rate test, whenever a filter is changed, whenever work is performed that could affect the filter system efficiency, and at intervals not to exceed six months between refuebng outages, it shall be demonstrated that:
(1.)' The removal efficiency of the particulate filters is not less than 99 percent based on a DOP test per ANSI N101.1-1972 para. 4.1.
(2.) The re novel efficiency of each of the charcoal filters is not less than 99 percent based on a l
Freon test.
}
c.
At least once each yr, removable charcoal cartridges shall be removed and absorption capability shall be demonstrated.
d.
Once per 24 months, automatic initiation of each l
branch of the Standby Gas Treatment System shall be demonstrated.
Amendment No. 40,232 182 a
JAFNPP 3.7 (cont'd) e.
Once per 24 months, 'nanual operability of the bypass valve for filter cooling shen be demonstrated.
f.
Standby Gas Treatment System Instrumentation Calibration:
differential Once/ operating pressure Cycle switches 2.
From and after the date that one circuit of the Standby 2.
When o.m circuit of the Standby Gas Treatment Gas Treatment System is made or found to be inoperable System becomes inoperable, the operable circuit for any reason, the following would apply:
shall be verified to be operable immediately and daily thereafter.
a.
If in Start-up/ Hot Standby, Run or Hot Shutdown mode, reactor operation or irradiated fuel handling is permissible only during the succeeding 7 days unless such circuit is sooner made operable, provided that during such 7 days all active components of the cther Standby Gas Treatment Circuit shall be operable.
b.
If in Refuel or Cold Shutdown mode, reactor operation or irradiated fuel handling is permissible only during the succeeding 31 days unless such circuit is sooner made operable, provided that during such 31 days all active components of the other Standby Gas Treatment Circuit shaN be operable.
3.
If Specifications 3.7.B.1 and 3.7.B.2 are not met, the
- 3. Intentionally Blank reactor shall be placed in the cold condition and irradiated fuel handling operations and operations that could reduce the shutdown margin shall be prohibited.
Amendment No. 10,SS,11",151,232 183 A
JAFNPP 3.7 (cont'd) 4.7 (cont'd)
^
c.
Secondary containment capability to maintain a 1/4 in. of water vacuum under calm wind conditions with a filter train flow rate of not more then 6,000 cfm, shall be demonstrated once per 24 months prior to refueling.
D.
Primary Containment isolation Valves D.
Primary Containment Isalation Valves 1.
Whenever primary containment integrity is required per 1.
The primary containment isolation valves survedlance 3.7.A.2, containment isolation valves and all instrument shall be performed as follows:
line excess flow check valves shall be operable, except as specified in 3.7.D.2. The containment vent and purge a.
Once per 24 months, the operable isolation valves valves shall be limited to opening angles less than or that are power operated and automatically initiated equal to that specified below:
shall be tested for sunulated automatic initiation and for closure time.
Valve Number Maximum Opening Anale 27AOV-111 40' b.
At least once per operating cycle, the instrument 27AOV-112 40' line excess flow check valves shall be tested for 27AOV-113 40*
proper operation.
l 27AOV-114 50*
27AOV-115 50*
c.
At least once per quarter:
27AOV-116 50*
27AOV-117 50*
(1.) All normally open power-operated isolation 27AOV-118 50*
valves (except for the main steam line and Reactor Building Closed Loop Coolmg Water System (RBCLCWS) power-operated isolation valves shall be fully closed and reopened.
Amendment No. 151,173,195,232
JAFNPP 4.7 BASES (cont'd) building isolation valves, leak-tightness of the reactor The in place testing of charcoal filters is performed using building and performance of the Standby Ges Treatment Freon or equivalent, which is injected into the system System. Functionally testing the initiatiag sensors and upstream of the charcoal filters. Measurements of the associated trip channels demonstrates the capability for Freon concentration upstream and downstream of the automatic actuation. Performing these tests prior to charcoal filters is made. The ratio of the inlet and outlet refueling will demonstrate secondary containment concentrations gives an overall indication of the leak capability prior to the time the primary containment is tightness of the system. Although this is basicaNy a leak epened for refueling. Periodic testing gives sufficient -
ter6 -ince the filters have charcoal of known efficiency confidence of reactor budding integrity and Standby Gas and ' c,kling capacity for elementaliodine and/or methyl n
Treatment System performance capability.
iodine, the test also geves an indication of the relative efficiency of the installed system.
The test frequencies are adequate to detect equipment deterioration prior to significant defects, but the tests are High-efficiency particulate filters are installed to menemize not frequent enough to load the filters, thus reducing their potential release of particulates to the environment. An reserve capacity too quickly. That the testing frequency is efficiency of 90 percent is adequate.to retain particulates adequate to detect deterioration was demonstrated by the that may be released to the reactor building following an tests which showed no loss of filter efficiency after 2 yr.
accident. This will be demonstrated by in-place testing of operation in the rugged shipboard environment on the with DOP as testing medium.
NS Savannah (ORNL 3726). Pressure drop tests across filter sections are performed to detect gross plugging or leak paths through the filter media. Considering the j
relatively short time that the fans maf be run for test purposes, plugging is unlikely, and the test interval of once per 24 months is reasonable. Duct heater tests will be conducted once per 24 months. Considering the simplicity of the heating circuit, the test frequency is sufficient.
l 1
L Amendment No. 232 195
.8
JAFNPP 4.7 BASES (cont'd)
- The test interval for filter efficiency was selected to minimize in order to assure that the doses that may result from a steam plugging of the filters. In addition, retention capacity in terms line break do not exceed the 10CFR100 guidelines, it is of milligrams of iodine per gram of charcoal will be necessary that no fuel rod perforation resulting from the demonstrated. This will be done by testing the charcoal once accident occur prior to closure of the main steam line isolation a year, unless filter efficiency seriously deteriorates. Since -
valves. Analyses indicate that fuel rod cladding perforations shelf lives greater than 5 yr. have been demonstrated, the test would be avoided for main steam valve closure times, including interval is reasonable.
instrument delay, as long as 10.5 sec.
O.
Primary Containment Isolation Valves For Reactor Coolant System temperatures less than 212 F, the containment could not become pressurized due to a The large pipes comprising a portion of the Reactor Coolant loss-of-coolant accident. The 212*F limit is based on l
System, whose failure could result in uncovering the reactor preventing pressurization of the reactor building and rupture of a
i core, are supplied with automatic isolation valves (except the blowout panels.
those lines needed for Emergency Core Cooling Systems 1
operation or containment cooling). Valve closure times are The primary containment isolation valves are highly reliable, adequate to prevent loss of more coolant from the have low service requirement, and most are normally closed.
circumferential rupture of any of these lines outside the Power operated primary containment isolation valves that can containment than from a steam line rupture. Therefore, be cycled during normal plant operations are cycled periodically.
isolation valve closure times are sufficient to prevent per the ASME Section XI Inservice Testing Program. Valves i
uncovering the core.
that can not be cycled during normal plant operations are tested once every 24 months.' The initiating sensors and associated trip channels are periodically checked to demonstrate proper response. This combination of testing adequately verifies operability of power operated and automatically initiated primary containment isolation valves.
l i
l L
l 1
. t Amendment No.173, 232 196 l
i
..m
-m m
m s m
. m
______.___m________,-_____..__t_-_s_-m_____..___
a JAFNPP 4.7 BASES (cont'd)
The main steam line isolation valves are functionally tested on a more frequent interval to establish a high degree of -
reliability.
The primary containtnant is penetrated by several small diameter instrument lines connected to the reactor coolant system. Each instrument line contains a 0.25 in. restricting orifice inside the primary containment and an excess flow check valve' outside the primary containment.
The RBCLCWS valves are excluded from the quarterly surveillance requirements because closure of these valves will eliminate the coolant flow to the drywell air and recirculation pump-motor coolers. Without cooling water, the drywell air and equipment temperature will increase and may cause damage to the equipment during normal plant operations.
Therefore, testing of these valves would only be conducted in the cold condition.
A list of containment isolation valves, including a brief description of each valve is included in Section 7.3 of the updated FSAR.
a Amendment No. 15',173, 203,232 197-4
.m_ _.
i JAFNPP 3.9 (cont'd) 4.9 (cont'd) 3.
From and after the time that one of the Emergency Diesel 3.
The emergency diesel generator system instrumentation i
Generator Systems is made or found to be inoperable, shall be checked dunng the monthly generator test.
i continued reactor operation is permissible for a period not to exceed 7 days provided that ti' two incomme power sources are avadable and that the amaining Diesel Generator System is operable. At the end of the 7 day period, the reactor shou be placed in a cold condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, unions the affected diesel generator i
system is made operable sooner.
i 4.
When both Emergency Diesel Generator Systems are 4.
Once every 24 months, the conditions under which the t'
made or found to be inoperable restore at least one Emergency Diesel Generator System is required ; vill be i
system to operable status within two hours or place the simulated to demonstrate that the pair of diesel i
i reactor in the cold condition within the following 24 generators will start, accelerate, force paraM, :mi hours.
accept the emergency loods in the prescribed sequerk '.
5.
Deleted 5.
Once within one hour and at least once per twenty-four hours thereafter whde the reactor is beme operated in j
accordance with Specifications 3.9.8.1, 3.9.B.2, or 3.9.8.3 the availabihty of the operable Emergency Diesei i
Generators sheE be demonstrated by manuel startmo and force paralleling where appbcable.
l 1
I i
I Amendment No. 30,96,444,443,490,484, 232 21e7
I i
JAFNPP 3.9 (cont'd) 4.9 (cont'd) 3.
From and after the time that both batteries are made
- 3. Once every 24 months, during shutdown, each station or found to be inoperable for any reason, the reactor bettery shot be subjected to a sorwce (duty cycle) shall be in a cold condition within 24 hrs.
test.'
- 4. Once every 60 months, during shutdown, each battery shen be subjected to a performance test (or modified performance test). This test shen verify that the bettery capacity is at least 80% of the manufacturer's rating.
l
- 5. Accelerated parformance testing (or modified performance test) shaN be conducted on any battery:
a) AnnueNy if capacity drops more than 1b% from its previous performance test (or modified performance test).
b) AnnuaNy if capacity is below 90% of manufacturer's rating.
c) AnnusNy if it has reached 85% of its serwce life with capacity <100% of manufacturer's rating.
di Once every 24 months if it has reached 85% of its service life with cepecity 2:100% of the manufacturer's rating.
i l
- 6. Each bettery charger shen be visueNy inspected weekly and a performance test conducted once every 24 h
months.
ll
- 7. Oncehnonth: open the bettery charger output breakers one at a time and observe performance for proper operation.
l
- i. a a,_ _
wn,-
I Amendment No. 44,467, 232 i
222 A
m--i4.Aa4a A
A.a._a s
e.p,a...4._____
a-4 an a-4d8-h - '--
A-h a-+d--
--+
4 L-1 4.
r JAFNPP 3.9 (cont'd) 4.9 (cont'd)
F.
LPCI MOV hulsoendent Power Sunolies F.
LPCI MOV Independent Power Sunches 1.
Every week the specific gravity, voltage and temperature of each pilot cou, and overall battery voltage shall be measured and chargers and inverters shen be visually inspected.
2.
Every three months the foNowing measurements shen be made:
s.
Voltage of each ceN to the nearest of 0.01v; b.'
Specific gravity of each ceN; c.
Temperature of every fifth ceN.
3.
Once every 24 months, each battery shall be subsected to a service (duty cycle) test.'
4.
Once every 60 months, each battery shall be subjected to a performance test (or modified performance test). This test shen verify that the battery capacity is at least 80% of the manufacturer's ratin0 g
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Amendment No. -30, M,406,46,232 2,22a 6
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I l
i JAFNPP j
3.9 (con'd) 4.9 icon'd)
F. LPCI MOV Indeoendent Power Sunolies F.
LPCI MOV Indeoendent Power Sunches 1.
Reactor shall not be made critical unless both independent 5.
Accelerated performance testing (or modified power supplies, includeng the batteries, iroverters and performance test) shen be conducted on any battery:
chargers and their associated buses IMCC-155 and MCC-165) are in service, except as specified below.
al Annually if capacity drops more than 10% from its previous performance test (or modified 2.
During power operation, if one independent power supply performance test).
becomes unavailable, repairs shall be made immediately and continued reactor operation is permissible for a period b)
Annually if capacity is below 90% of L
not to exceed 7 days u ' ess the unavadable trag is made manufacturer's rating.
l operable sooner. Froer and after the date one a the mdependent power seas is made or found to be c)
Annually if it has reached 85% of its service inoperable for any reason, the following would apply:
life with capacity <100% of manufacturer's rating-l
- a. The other independent power supply including its charger, inverter, battery and associated bus is d)
Once every 24 months if it has reached 85%
of.its service life with capacity a:100% of the manufacturer's rating.
- b. Pilot ceN voltage, specific gravity and temperature and overall battery voltage are measured immediately and 6.
Each bettery charger and inverter shall be visually l
weekly thereafter for the operable independent power inspected weekly and a performance test conducted l
aupply battery.
once every 24 months.
- c. The inoperable independent power supply shall be 7.
Once/ month: open the battery energer A-C input i
isolated from its associated LPCI MOV bus, and this breakers one at a time and observe performance for bus will be manuaNy switched to its alternate power proper operation.
source.
i 232 Amendment No. -44,400, 222b
JAFNPP 4.9 BASES (cont'd)
D.
Not Used followed by a constant discharge current (temperature corrected) for the performance test.
E.
Batterv System The purpose of the modified performance test is to demonstrate Measurements and electrical tests are conducted at specified the battery has sufficient capacity to meet the system design intervals to provide indication of cell condition and to determine requirements and to provide trendable performance data to the discharge capability of the batteries. Performance and compare the available capacity in the battery to previous capacity service tests are conducted in accordance with the test results. The modified performance test may be performed in l
recommendations of IEEE 450-1995.
lieu of the battery service test.
The battery service (duty cycle) test demonstrates the capacity of The station batteries are required for plant operation, and the battery to meet the system design requirements. When a performing the station battery service test and performance (or service ted is used on a regular basis, it will reflect maintenance modified performance) test requires the reactor to be shut down.
practices. The FitzPatrick design duty cycle loads are determined by a LOCA concurrent with a loss of normal and F.
LPCI MOV Indanandent Power SMv reserve power.
Measurement and electrical tests are conducted at specified The performance (discharge) test is a test of the constant current intervals to provide indication of cell condition, to determine the capacity of a battery and can be conducted with the battery in an discharge capability of the battery. Performance and service as-found condition after being subjected to an equalizing charge.
tests are conducted in accordance with the recommendations of if performance testing is to be used to reflect baselined battery lEEE 450-1995.
trending capacity, then special conditions (including equalizing) are required to establish the battery in an as-known condition G.
Ranciar Protectinn Power Sunnhac prior to the test. If performance testing is to be used to reflect maintenance practices as well as trending, the equalizing charge Functional tests of the electrical protection assemblies are can be omitted.
conducted at specified intervals utilizing a built-in test device and i
once per operating cycle by performing an instrument calibration The modified performance test is a composite test which which verifies operation within the limits of Section 4.9.G.
envelopes both the service test and performance test
'equirements. The modified performance test discharge current r
envelopes the peak duty cycle loads of the service test Amendment No. 80,76,404,467,489,490,232 226 b