ML20205T181
| ML20205T181 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 11/07/1988 |
| From: | Capra R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20205T172 | List: |
| References | |
| NUDOCS 8811140161 | |
| Download: ML20205T181 (3) | |
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UNITED STATES
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E NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20655 i
POWER AUTHOR,ITY OF THE STATE OF NEW YORK DOCKET NO. 50-333 JAMES A. FITZPATRICK NUCLEAR POWER PLANT
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AMENDMEN1 TO FACILITY OPERATING LICENSE
%endment No.116 License No. DPP-59 j
1.
The Nuclear Pegulatory Comission (the Comissioni has found that:
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Tr.c application for amendment by Power Authority of the Stata of New York (the liceasee) dated August 24, 1988, cceplies with the standards and requirements of the Atomic Energ.y Act of 1954, as amended (the Act) and the Comissior's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in cerformity with the application, the provisions of the Act, and the rules and regulations of l
the Comission; 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 Comission's regulationsi l
0.
The issuance of this amendment will not be ininical to the corron defense and security or to the health and safety of the public; and E.
The !ssuance of this amendment is in accordance with 10 CFR Part i
51 of the Comission's regalations and all applicable requirements have been satisfied.
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2.
Accordinaly, the license is amended by changes to the Technical S'ecifications as indicated 4. the attachment to this license 4
amendment, and paragraph 7.C.(?) of Facility Operating icense 1
No. OPR-59 is hereby amended to read as follows:
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(2) Technical Specifications l
The Technical Specifications contained in ALpandices A and B, as revised through Amendment No.116, are hereby incorporated in the license. The licensee shall i
operate the facility in accordance with the Technical i
Specifications.
3.
This license amsndment is effective as of the date of its issuance.
l FOR THE NtJClfAR REGULATORY COMMIS$10N TJ Ja-.C p Robert A. Capra, Director Project Directorate I-1 f
Division of Reactor Projects. I/II t
Attachment:
Changes to the Technical Specifications Date of Issuance: Novcaber 7, 1988 i
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UNITED STATES NUCLEAR REGULATORY COMMISSION e
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f WASHINGTON. D. C. 20665
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ATTACHMENT TO LICENSE AMENDMENT NO. 1ia FACILITY OPERATING LICENSE NO. DPR-59 DOCKET NO. 50-333 i
Revise Appendix A as follows:
Remove Pages Insert Pages 4
vii vii 105 105 i
f 107 107 108 108 f
i 109 109 109a 109a i
110 110 111 111 i
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JAFNPP LIST OF FIGUREj Z.122.Lt Tit 1e EAER 3.1-1 Manual T'3w Control 4?a
[
l 3.1-2 Operating Limit MCPR versus 47b 4.1-1 Graphic Aid in the Selection of an Adequate Interval Betwqen Tests 48 4.2-1 Test Interval vs. Probability of System Unavailability 87 h
3.4-1 Sodium Pentaborate Solution 34.7 B-10 Atom % Enriched l
volume-Concentration Requirements 110 3.4 2 Saturaticr. Te perature of Enriched So'ium Pentaborate l
Solution 111 3.5-1 Thermal Power and Core Flow Limits of Specifications I
3.5.J.1 and 3.5.J.2 134
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3.5-6 (Deleted) 135d 3.5-7 (Deleted) 135e 3.5-8 (Deleted) 135f 3.5-9 KAPLHGR Versus Planar Average Exposure Reload 4.
P8DRB284L 135g 3.5-10 MAPLH3R Versus Planar Average Exposure Reloads 4 & 5.
P8DRB299 135h 3.5-11 MAPLHGR Versus Planar Average Exposure Reload 6, BP8DRB299 1351 3.6-1 Reactor Vessel Pressure-Temperature Limits 163 4.6 1 Chloride Stress Corrosion Test Results at 500'T 164 6.1-1 Management organization Chart 259 6.2 1 Plant Staff Organisation 260 Amendment No. g, g, pf, p(, Jf, J4, g, J4,1/ 116 vii
^^^^^ O.L. 690824 PDR ADOCK 05000333 1
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JAfEPP 3.4
(,I M IT I NG_C0tGIT I ON SJOR_QP E R AT I ON 4.4 StJRVEYI.LANCr._ REQUIRD4ENTS 3.4 STANDI4_!,iDUID_ CONTROL _ SYSTEM 4.4 STANDf5Y LIQtIID_ CONTROL SYSTEM Applicability:
Applicability:
Applies to the operating status of the Standby Liquid I.pplies to the pariodic testing requirements for the Control System.
Standby Liquid Control System.
Objective:
Objective To assure the availability of a system with the To verify the operability of the Standby Liquid capability to :. hut down the reactor and maintain the Control System.
chutdown condit ion without control rods.
Specilications Specilication:
A.
NoImol_Operetjan A.
N_01ma l_Opetotion During periods when fuel is in the reactor and The operability of the Standby L: quid Control System prior to startup from a cold condition, the shall be verified by performance cf the following 5 tan.1by Liquid Control System shall be operable tests:
except as specified in 3.4.B below.
This system need not be operable when the reactor is in the 1.
At Jeest once pet month -
cold condition, all rods are fully inserted and Specification 3.3.A is met.
Demineralized water shall be recycled to the test tank.
Pump minimum flow rate of 50 gpm l shall be verified against a system head of Z 1,275 psig.
2.
At JfDst Once dudng each operating cycle Manually initiate the system, except the cuplosive vafves and Amendment No.
1 I (>
105
. _ _ _ _. = - _
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3.4 (Cont'd) 4.4 (Cont *d) 1 l
C.
Sodiuml sntabofete_G91wtion C.
Sodium _Pentaborate_S91, tion 1
j The standby liquid control solution tank shall The availability of the proper boron bearing j
g contain a heron bearing solution with a minimum solution si. ell be verifled by performance of the
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l sarichment of 34.7 atom percent of B-10 that following tests:
j satisfies the volum*-concentration requirements of rig. 3.4-1 at all times when the Stand):y 1.
At lejst onct oer month -
Liquid Control dystwe is required to be operable i
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and the solution temperature including that in Boron concentration shall be determined. In j
the pump suction piping shall not be less than addition, the boron concentration shall be 9
j the temperature presented in Fig. 3.4-2.
Tank determined any time water or enriched sodium l
heater and the heat tracing system shall be pe.itaborate is added or if the solution 3
j operable whenever the SLCS is required in order teJperature drSps below the limits specified i
to maintain solution temperature in accordancs Lf rig. 3.4-2.
with rig. 3.4-2.
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2.
At least once per day -
I Solution volume and the solutions temperature shall be checked.
3.
At least opsg per opgfating Cyclf -
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- a. The temocrature and level elements shall be calibrated.
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- b. Enrichment of 75-10 (in aton percent) i shall 17 checked.
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If specifications 3.4.A through C are mot met, j
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the reactor shall be in the cold condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
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Amendment No. I16 107 i
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_ _ _ _ _ _ _ _ _ _ _ ~.. _ _ _ _ _. _ _.. _ _ _ _, _. -.... = _. _. - _. _ _ _ _ _ _ _
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JAFNPP 3.4 and 4.4 BASES The technical specifications assure that the minimum injecting time for the SLC System is 44 A.
Norm @l jQperatjpn minutes and maximum injection time 96 minutes, thus meeting the plant design basis. In addition The design objective of the Standby Liquid to meeting its original design basis, the system Control System is to bring the reactor from must also satisfy the Anticipated Transient f ull power t o cold, menon-f ree shutdown Without Scram (ATWS) Rule, 10 CFR 50.62 paragraph assuming that no control rods can be (c) (4).
inserted. To do this, the Standby Liquid Control System is designed to inject a The ATWS Rule requires a minimum flow cepacity quantity of boron which produces a minimum anc boron content equivalent in control capacity concentration equivalent to 660 ppa of to 86 gallons per minute of 13 weight percent natural boron in the reactor core.
Six sodium pentaborate solution. The "equivalent in hundred and sluty ppn boron concentration in control capacity" wording was clarified in the reactor core is required to bring the Generic Letter 85-03.
Equivalence can be reactor froo full power to a subcritical obtained by increasing the flow, boron condition considering:
concentration, or boron enrichment. For the FitzPatrick plant, the rule is met by using boron o the reactivity insertion due to temperature enriched to 34.7 aton percent boron-10 and a decrease cassed by changing water density, pumping rate of 50 gpe.
The method used to show o decay of menon poisoning equivalence with 10 CFR 50.62 is described in o uncertainties and biases in the analyses and NEDE - 31096 - P-A :
o 25% margin for potentially imperfect mixing of the sodium pentaborato soluticn in the E/19.8 x C/13 x HQ51/M x Q/86 21 1
reactor water.
where The desige basis of the SLCS requires that Injection be completed in a time period no E = horon enrichment = 34.7 atom %
i less than 23 minutes and no greater than 125 0 = SLCS flow rate = 50 gpm minutes. The upper time limit (125 min) for M=
mass of water in reactor vessel and complete injection of the sodium pentaborate recirculation system at hot rated condition solution was selected to override the rate of 491,700 lbs. for FitzPatrick plant reactivity insertion due to cooldown of the M251 = mass of water in vessel and recirculation reactor following the senon poison peak.
The system at hot rated condition (628,300 lower time limit (23 min) is based on the Ibs.) for 251 - inch diameter vessel plant need to allow adequate mixing, so the boron C=
sodium pentaborate solution concentration does not circulate in uneven con;entrations (weight percent) greater than or equal to that could cause local power fluctuations.
10 percent Amendment No. g,116 108
JAFNPP ATWS requirements are satisfied at all The relief valves in the Standby Liquid Control concentrations above 10 weight percent for a System protect the system piping and positive minimum enrichment of 34.7 atom percent of B-10.
displacement pumps, which are nominally designed for 1,500 psig, from overpressure. The pressure Figure 3.4-1 shows the permissible region of relief valves discharge back to the. standby operation on a sodium pentaborate solution volume liquid control pump suction line.
versus concentration graph. This curve was developed for 34.7% enriched 5-10 and a pumping B.
Ope r a t i on_w i th_I nope r abl eJompo ec n t s rate of 50 gpe.
Each point on this curve provides a minimum of 660 ppe of equivalent only one of two standby liquid control pumping natural boron in the reactor vessel upon circuits is needed for operation.
If one circuit injection of SLC solution. At a solution volume is inoperable, there is no immediate threat to of 2200 gallons, a weight concentration of 13%
shutdown capability, and reactor operation may sodium pentabterate, enriched to 34.7% boron-10 is continue during repairs. Assurance that the needed to me<st shutdown requirements. The remaining system will perform its function and maximum storage volume of the solution is 4780 that reliability is good is obtained by gallons which is the net overflow volume la the demonstrating pump operation in the operable SLC tank.
circuit at least daily.
Baron concentration, isotopic enrichment of C.
SodiumlestatparateAlyt. ion boron-10, solutloa temperature, and volume are checked on a frequency adequate to assure a high To quard against precipitation, the solution, reliability of operation of the system should it including that in the pump suction piping, is ever be required. Experience with pump kept at least 10*F above saturation temperature.
operability indicates that monthly testing is Figure 0.4-2 sb9 s the saturation temperature adequate to detect if failures have occurred.
Including Mr'F margia as a function of sodlum pentabo ate solutlos concentration. Tank heater The only practical time to test the Standby and 'aeat tracing system are provided to assure Liquid Control System is during a refueling compliance with this requirement. The set points outage and by initiation from local stations.
for the automatic actuation of the task heater Components of the system are checked periodically and heat tracing system are established based on as described above and make a functional test of the solution concentratloa. Temperature nd the entire system on a fregues.cy of more than liquid level alarms for the system annunciate in once each refueling outage unnecessary.
A test the control room.
Pump operability is checked on of cuplosive charges from one manufacturing batch a frequency to assure a high reliability of is made to assure that ti.e charges are operation of the system should it ever be satisfactory. A continuous check of the fiting required.
l circuit continuity is provided by pilot lights in the control room.
Amendment No. }4 116 109
JAFNPP Once the solution is prepared, heros concentration does not vary, unless more enriched sodium penta-borate or more water is added. Invel indications and alarms ledicate whether the solutlem volume has changed which might Indicate a possible solution concestration change. The test interval i
has been established considering these factors.
Boron enrichment (B-10 atom percent) does not very with the addition of enriched sodium pentaborate meterial or water to the SLC task provided 34. h enriched (B-10 atom percent) is added. Therefore, a check once per operating cycle is adequate to ensure proper enrichment.
1 Amendment No. I16 309a
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