ML20033E815
| ML20033E815 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 03/05/1990 |
| From: | Capra R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20033E816 | List: |
| References | |
| NUDOCS 9003140294 | |
| Download: ML20033E815 (10) | |
Text
8[goso, k UNITED STATES t
e-NUCLEAR REGULATORY COMMISSION n
,I e
WASHINGTON, D. C. 20555 i
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?... 9 POWER AUTHORITY OF THE STATE OF NEW YORK I
l DOCKET NO. 50-333 i
JAMES A. FIT 2 PATRICK NUCLEAR POWER PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.154 I
License No. DPR-59 h
1.
The Nuclear Regulatory Comission (the Comission) has found that:
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A.
The application for amendment by Power Authority of the State l-of New York (the licensee) dated January 17, 1989 and amplified by l
1etter dated October 25, 1989, complies with the standards and requirementsoftheAtomicEnergyActof1954,asamended(theAct) l.
and the Comission's rules and regulations set forth in 10 CFR l
Chapter I; 1
B.
The facility will o)erate in conformity with the application, the provisions of t1e Act, and the rules and regulations of j
the Comission-C.
Thereisreasonableassurance(i)thattheactivitiesauthorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be l.
conducted in compliance with the Comission's regulations; D.
The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; and i
E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and al? applicable requirements have been satisfied.
l 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license o
f amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-59 is hereby amended to read as follows:
9 9003140294 900305 t
l PDR ADOCK 05000333 P
PNU i
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i (2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.154, 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 to be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION Y' Y Robert A. Capra, Director Project Directorate I-I Division of Reactor Projects - I/II Office of Nuclear Reac.or Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: March 5, 1990 O
p
'n.:
i ATTACHMENT TO LICENSE AMENDMENT tl0.154 FACILITY OPERATING LICENSE NO. DPR-59 DOCKET NO. 50-333
)
Revise Appendix A as follows:
Renove Pages Insert Pages 183 183 i
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185 185 i
186 186 191 191 192 192 197 197 W
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JAFNPP 3.7 (cont'd) 4.7 (cont'd)
At least once per operating cycle, manual operabelsty e.
of the bypass valve for filter cooleng shall be demonstrated.
f.
Standby Gas Treatment System Instrumentation Calibration:
1 differential Once/ operating pressure Cycle switches 2.
From and after the date that one circuit of the Standby Gas Treatment System is made oi found to be inoperable for 2.
When one circuit of the Standby Gas Treatment System any reason, the following would apply:
becomes inoperable, the operable circuit shall be verified to be operable immediately and daily thereafter.
a.
If it: Start-up/ Hot Standby, Run or Hot Shutdown rnode, reactor operation or irradiated fuel handhng is permissible only during the succeedirs 7 days unless such circuit is sooner made operable, provided that during such 7 days all active components of the other Standby Gas Treatment Circuit shall be operable.
b.
If in Refuel or Cold Shutdown mode, reactor operation or irradiated fuel handling is permissible only duiing the succeeding 31 days unless such circuit is sooner made operable, provided that during such 31 days all active coinponet.ts of the other Standby Gas Treatment Circuit shall be operable.
3.
If Specifications 3.7.B.1 and 3.7.B2 are not met, the reactor shall be placed in the cold condition and irradiated
- 3. Intentionally Blank fuel handling operations and operations that could reduce the shutdown margin shall be prohibited.
Amendment No. }6,p6, ped 154 183 r
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'a JAFNPP 3.7 (cont'd) 4.7 (cont'd) 4.
Whenever ' primary containment integrity it required as 4.
Valve 27MOV 120 shall be verified closed when specified in Section 3.7.A2. Valve 27MOV-121 shall be contawiment integrity is established, and then once per used for inerting or desnertng.
month.
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l Amendment No.154 183a u
c JAFNPP
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4 3.7 (cont *d)
' 4.7 (cont'd)
Secondary containment capatmisty to mavain a 1/4 c.
in. of water vacuum under calm wind conditions with a filter train flow rate of not more than 6,000 cim, shall be demonstrated at each refueleng outage prior to refueling.
D.
Primary Containment Isolation Valves D.
Primary Containment Isolation Valves 1.
The primary contaenmert isolation valves surveillance shall i
1.
Whenever primary containment integrity is required per be performed as follows-3.7.A.2, containment iso!ation valves specified in Table 3.7-1 and all instrument line excess flow check valves shall a.
At least once per operating cycle, the operable be operable, except as specified in 3.7.D 2. The closure isolation valves that are power operated and times for the valves shall be as specified in Table 3.7-1.
automahcally initiated shall be testes for sanulated The contavnment vent and purge valves shall be limited to automatic wwtahon and for closure times as opening angles less than or equal to that specif:ed below:
specified in Table 3.7-1.
I Valve Number Maximum Opening Angle b.
At least once per operating cycle, the instrtment line 27AOV-111 4(T excess flow check valves shall be tested for proper 27AOV-112 4(T.
operation.
c A
once per wm OV-11 SCP O
6 50*
(1.)
All normally open power-opvated isoitiion l
l 27AOV-117 50 valves (except for the main stream line and l
27AOV-118 50 hw M Loop %
l Water System (RBCLCWS) power-operated solation valves) shall be fully closed and reopened.
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l Amendment No. 154 f
185 reg' s
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4 JAFNPP 3.7 (conrd) 4.7 (cont'd)
(2.)
With the reactor at reduced power level, trip rnain steam isolation va8ves and venfy closure time.
d.
At least twice per week, the main steam line power-operated isotahon valves shall be exerc sed by partial closure and subsequent reopenmg The ROCLCWS esolabon valves shall be fully closed e.
and reopened any time the reactor is in the cold 2.
With one or more of the isolation vanes listed in Table 3.7-1 inoperable, maintain at least o"s iso'ation valve opwable in each affected penetr&.rhu is open and:
2.
Whenever an isolahon valve listed in Table 3.7-1 is a.
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$e vh(s) to we status g
no erable, the positen of at least one other valve in each line having an inoperable valve shall be recorded daily.
b.
Isolate each affected penetration withm 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by use of at least one deactivated aJtomahc valve secured in the closed posihon. Isolabon valves closed to satisfy these requirernents may be reopened on an intermittent base under edera Gativecontrol;or Isolate each affected penetrabon within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by c.
use of at least one closed manual valve c a blind fenge.
3.
If Spec;Tcatic=w 3.7.D.1 or 3.7.D2 cannot be met, an orderly shutdown shall be initiated and the reactor shall be in cold condition withm 24 hrs.
Amendment No. Jg4 154 186
JAFNPP 3.7 BASES (cont'd) complete containmert system, secondary contammerd is rW whenever sigrA;is 4 chas ages in fdter effoency occur.
required at aN tunes that pnmary contamment is required as Tests (11) of k opiegnated charcoal identical to that used in the.
weR as dunng refusing.
fiiter:s indicate that shelf ide up to 5 yr leads to only mmor The Standby Gas Treatment System is desegned to filter and decreases M nwthyl & rM %.
exhaust the reactor bueldog ah ncsphere to the main stack The 99 percent efficency of the charcoal and particulate filters donng secondary contamment isolation conditeons with a is sufficient to prevent exceeding 10CFR100 gudelines for tha minimum release of radicia.hve materials from the roccior accide.hanalyzed. Theanalysisof theloss-d-coolant
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building to the environs. Both standby gas treatmem fans are accident assumed a charcoal filter efEccency d 90 percent, a designed to automahcally s'. art upon contamment isolabon; particulate filter efficency of 90 percent, and TID 14844 fisseon however, only one fan is required to mamtam the reactor product source term. Hence, requong 99 percent efEcsency for building pressure at approxwnately a negative 1/4 in. water both the charcoal and partculate filters promdes adequate gage pressure; aR leakage should be in-leakage. Each of the margin. A heater mamtains relative humidity below 70 percent two fans has 100 percent capacity.11 one Standby Gas in order to assure the effo~ ent removal of methyl sodme on the Treatment System circuit is inoperable, the other circuit must impregnated charcoal filters, ba tested daily. This substanisates the avedabsiity of the operable circuit and results m no added risk; thus, reactor h wM N StW h Tre Sp (SGTS operation or refueling operation can conhnue. If nerther circuit must be assured if a desegn bases loss d coolant M 4 is operable, the Plant is brought to a w umn. where the M h Nis % WW systemis M r@d he SGTS. Mom m to the SGTS t
is via 6 inch Valve Number 27MOV.121. Sece the maximum While only a small amount of particulates is released form the flow through the 6 inch line follomng a design bases LOCA is Pressure Suppression Chamber System as a result of the loss-within the design capabdities of the SGTS, use of the 6 inch line of-coolant accident, high-efficency particulate filters are assures the operability of the SGTS.
specified to momize potenbal particulate release to the D~
Pnmary Contamment isotahon Vaives environment and to prevent cloggog of the iodme filter. The high-efficency filters have an efficsency greater than 99 percent Double isolation valves are provided on lines perehning the for particulate matter larger than 03 micron. The mnmum primary corta r.T. erd and open to the free space iodine removal efficiency is 99 percent. Filter banks wiR be Amendment No. 154 191
w JAFNPP 3.7 BASES (cont'd) 4 of the contamment. Closure of one of the valves in each line would be sufficient to mantam the integnty of the Pressure Suppressson System. Automahc initiation is required to minimize the potenhal leakage paths from the contamment in
' the event of a loss 4 coolant r=,cidant The contamment isolabon valves on the contamment vent and purge lines may be open for safety related reasons. Safety related reasons eclude, tut are not Imted to, the followog-inerting or de-inerting pnmary contamment; mamtammg contamment oxygen concentration; mantaning drywell'and suppression pool atinu.piisic pressures; and mantaming the
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differential pressure between the drywell and suppression pool.
l These valves have been modified to limit the maxarnum angle of openog as shown in 3.7.D.1.
Nine remote n.anual isolation valves have been added to the Reactor Busidmg Closed Loop Coolmg Water System (RBCLCWS) in order to comply with 10 CFR 50 Appendix A GDC 57; These vdves are air operated (with solenoid pilot valves), normally open, and are designed to fail "open on loss of electrical power or "as is" upon loss of instrument air. Each AOV is provided with a Seestmc Class I accumulator tank to allow operation of the valves upon loss of instrument air up to 2 full valve cycles. The fail-open design permsts continued operation of the system to supply water to the recirculahon purremotor coolers and drywell coolers dunng normal operation and as necessary under acodent conditions. If there is a postulated accident, and in6cidiots of leakage from RBCLCWS appear, the operator will selectively close the AOV's affected to provide contamment isolabon.
t Amendment No 154 192
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JAFNPP l
4.7 BASES (cont'd) l operatility results in a more reliable system.
The main steam line isolabon valves are furdicnWy tested on a more frequent interval to estabbsh a high degree of rehability.
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The primary contamment is_ penetrated by several small diameter instrument lines connected to the reactor coolant system. Each instrument hne contains a 0.25 in. restricFng orifice mssde the primary contamment and an excess flow check valve outssde the pnmary contamment.
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The RBCLCWS valves are excluded from the quarterly l
surveellance requirements because closure of these valves will eliminate the coolant flow to the drywell air and recirculation pump-motor coolers. Without coolog water, the drywell air and equipment temperature will increase and may cause damage to the equepment during normal plant operations.
1 Therefore, testing of these valves would only be conducted in l
the cold condition.
Amendment No. 154 197
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