ML20009A812
| ML20009A812 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 07/07/1981 |
| From: | Ippolito T Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20009A811 | List: |
| References | |
| NUDOCS 8107140252 | |
| Download: ML20009A812 (12) | |
Text
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UNITED STATES NUCLEAR REGULATORY COMMISSION y
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WASHINGTON, D. C. 20555 5,....../
5 POWER ' AUTHORITY '0F 'THE STATE ~ 0F NEW ' YORK DOCKET'NO. 50-333 JAMES A.'FITZPATRICK NUCLEAR' POWER' PLANT
, AMENDMENT ~TO' FACILITY OPERATING' LICENSE Amendment No. 57 License No. DPR-59 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by the Power Authority of the State of New York (the licensee) dated June 24, 1981, complies with.t he 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; B.
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 requirements have been satisfied.
2.
Accordingly, Facility Operating License No. DPR-59 is hereby amended by revising paragraph 2.C (2) and adding paragraphs 2.C.(4) and 2.C.(5) to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 57, are hereby incorporated in the license.
The licensee shall operate'the facility'in accordance with the Technical Specifications.
0107140252 010707 PDR ADOCK 05000333 P
PDR 3
b
1.
(4) ; Systems ' Integri ty k
The licensee shall' implement a -program to reduce' leakage from the systems outside containment that would or could contain highly radioactive fluids during a serious transient or accident to as low as practi cal 'l evels. This program shall include the. fo} lowing:
2 1.
Provisions establishing maintenance and periodic visual inspection requirements, and T
2., Leak test.requirem2nts for.dhe systems at a_ frequency not to exceed operating cycle inte,rvals.
(5) Io' dine Monitoring The licensee shall implement a program which will ensure the capability to accurately determine the airborne iodi'ne concentration in areas vital to the mitigation of or. recovery from an accident.
This program shall include the following:
1.
Training of personnel, 2.
Procedures for monitoring, and
-3.
. Provisions for maintenance of samplinggnd analysis equipment.
s.-
- 3.- This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION WCA 5.jg, Thomas Ippolito, Chief Operating Reactors Branch #2 Division of Licensing
Attachment:
Changes to the Technical
-Specifications
!Date of Issuarice: July 7,1981 I
L 9
w c-4..
ATTACHMENT TO LICENSE AMENDMENT'NO. 57 FACILITY -0PERATING ' LICENSE 'NO. DPR-59
' DOCKET'NO.'50-333 Revise Appendix A as follows:
Remove Insert
-76 76-76a 76a
-76b 76b 84 84
-85 85
~
248 248 248a 248a 249 249 260 260 r.
l 4
TABLE 3.2-6 SURVEILLANCE INSTRUMENTATION
- a' 4
Miminum No.
of Operable No. of Channels Instrument Type Indication
.Provided
- Channels Instrument' and Range by Design Action (Reactor Level Indicator)
(13) ( 2) l'
(
(Note 3) 0 - +60
)
,5 2
.(
)
(Reactor Level Recorder )
(
(Note 4) 0 - +60
)
1 Reac' tor Level Indicator
-150 - +60 2
(2)
(Reactor Pressure Indicator
-)
/
(
(Note 5) 0-1200 psig) 5 (1) (2) 2
(
)
Q*,
(Reactor Pressure Recorder
)
(
(Note 6) 0-1200 psig)
(Drywell Pressure (Narrow Range)-
\\
(
(Narrow Range)
Indicator
)
(
I}ecorder
)
(
30 - 19 psia )
,,(2) 1
)
2 (Drywell Pressure (Wide Range) )
(
(Wide Range)
Indicator
)
(
Recorder.
)
,1 -
(
0- 100 psia )
(Drywell Tempera ture Indicator
)
(
50 - 2500 F
)
2
(
).
4 (1) (2)
(Drywell Temperature Recorder
)
50 - 3500 F
)
(Suppression Chamber Indicator
)
(Temperature 50 - 2500 F
)
2
(
)
4 (1) (2)
(Suppression Chamber Reco.-de r
)
(Temperature 50 - 3500 F
)
Amendment No. XA, 40, 57 76
~
TABLE 3.2-6 SURVEILLANCE INSTRUMENTATION
~
Minimum No.-
~
cf Operable No. of Channels
~
In;trument Type Indication Provided Chrnnels Instrument and Range by Design Action'
-(Suppression Chamber Indicator
)
(Water Ievel Recorder
)
( (Wide Range)
-72 to + 72 inches) 1
(
)
2 (2)
(Suppression Chambar Indicator
)
(Water Level Recorder
)
( (Harrow' Range)
-6 to +6 inches
)
N/A Control Rod Indicator 1
(7)
Position Indication Position 00 to 48 2
Source Range Indicator 4
(8).
Monitors Recorder f
1 to 10' cps 3
Intermediate Indicator 8
(8) (9)
Range Monitor Recorder 10-4 to 40% Rated Power 2
Average Pc"cr Indicator 6
(8) (9)
Range Monitor Recorder 0-125% Fbted Power 1
Drywell-Suppression Recorder 2
(2)
Chamber Differential O to 5 psi Pressure Computer 0 to 5 psi 1
Safety / Relief Valve Indicator 2
(12) (11)
Position Indicator Open/ Closed (Note 10)
NOTES FOR TABLE 3.2-6 1.
From and af ter the date that the minimum numner of operable instrument channels is one less than the minimum number specified for each parameter, continued operation is permissible during the succeeding
- 30. days unless the minimum number specified is made operable sooner.
i Amendment No. 57 76a
PKMElm FOR-TABLE 3.2-6
' (CONTINUED) -
2.-
In'the event that all indications of this parameter +s' disabled and.such indication'crnnotIbe -
- restored in six -(6) hours, an orderly shutdown shall be initiated 1and the: reactor: shall be'in. e '-
a Hot Shutdown, condition'in six (6) hours and a Cold-Shutdown condition'in the;following eighteen'(18)1 hours1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
3.
Three.(3). indicators from' level instrument channel A, B,
& C. Channel A or B are, utilized for feedwater control, reactor water high.and low -level al' arms,7 recirculation pump (runback. 'High.
~
level trip of main. turbine and feedwater pump turbine' utilizes channelaA, B,
&'C..
- 4. 'One-(1) recorderutilized.thesameleve1'instrumentchannelasselected},forfeedwatercontrols
-5. -Three (3) indicators from reactor pressure instrument channel.A, B,
& C. Channel-A or B are 1
utilized for feedwater control and reactor pressure high. alarm.
6.
One (1) recorder. Utilizes. the same reactor pressure instrument channel as selected for i
feedwater control.
7.
The position of each of the 137 control rods is monitored by the F ai Position Information System. For control rods in which the position is unknown,' refer to Paragraph 3.3.A.
31.
8.
Neutron monitoring _ operability requirements are specified by Table'301-1 and Paragraph 3.3.B.4.
9.
A minimum of 3 IRM or 2 APRM channels respectively must be operable (or(tripped) in each' safety. system.
g 10.
Each Safety Relief Valve is equipped with hyo primary acou'stical detectors (of which one is in
. service). A thermocouple detector serves as a secondary indicator.
4>
11.
From and af ter. the date that none of the acoustical detectors is operable' but the. thermocouple is operable, continued operation is permissible until the next outage in;which..a. primary containment entry is made. Both acoustical detectors shall be made operableJprior to restart..
12.
In the event that both. primary and secondary indications of this~ parameter for any one valve are disabled and neither indication can be restored in forty-eight '(48) hours, an orderly I
shutdown shall be initiated and the reactor shall be in a Hot Shutdown condition in twelve (12). hours and in a Cold Shutdown ~within the next twenty-four- (24) hours.
1 13.
From and after the date that the minimum number of operable ~ instrument channels is one less than the minimum number specified for each parameter, continued operation is permissable i
during the succeeding 7 days unless the minimum number specified is made operable sooner.
Amendment No.
48,'57 76b I
o
~
v TABLE 4.2-6 MINIMUM TEST AND CALIBRATION FREQUENCY FOR SURVEILLIANCE INSTRUMENTATION' INSTRUMENT CHANNEL CALIBRATION FREQUENCY INSTRUMEffr ' CHECK 1.)
Reactor Water Level
-Once/6 moaths Once Each' Shift
- 2. ). Reactor Pressure Once/6 months Once Each Shift
~
3.)
Drywell Pressure Once/6 months Once Each Shift
. 4. )
Drywell Temperature Once/6 months Once Each Shift 5.)
Suppression Chamber Temperature once/6 months once Each Shift 6.)
Suppression Chamber Water Level Once/6 months Once Each Shift 7)
Control Rod Position Indication N/A Once Each Shift 8.)
Neutron Monitoring (APRM)
Five/ week Once Each Shift 9.)
Neutron Monitoring (IRM and SRM)
Note 10 Note 10 10.)
Drywell-Suppression Chamber Differential Pressure 06ce/6 months Once Each Shift 9
11.)
S.afety/ Relief Valve Position Indicator (Primary)
Note 11 Once/ Month 12.)
Safety / Relief Valve flote 11 Once/ Month Position Indication (Secondary)
[, jg, 57 04 Amendment No.
~
m m
s NOTES FOR TABLES 4.2-1 'I11ROUGI 4. 2-6 1.
Initislly once every month until acceptance failure rate 8.
Uses same instrumentation as Main Steam data are cvailables thereafter, a request may be made to the Line itigh Radiation. 'See Table 4.1-2. -
l NRC to change the test frequency. The compilation of instrument failure rate data may include data obtained from 9.
See Technical Specification ~1.0.F.4,.
other boiling
.t,er reactors for which the same design Definitions, for meaning of term, instrument operate in a environment similar to that of
" Instrument Check".
0 5 7'rpp.
10.
Calibration and instrument
.k surveillance 2.
Functional tests, calibrations and instrument checks are not for SRM and IRM Instruments are as specified required when these instruments are not required to be in Table 4.1-1, 4.1-2, 4.2-3.'
tre tripped.
Functional tests shall be operabic or performed before each startup with a required frequency not 11.
Functional test is performed once each to exceed once per week.
Calibrations shall be performed operating cycle.
prior to each startup or prior to preplanned shutdowns w?th a required frequency not to exceed once per week.
Instrument checks shall be performed at least once per day f
during these periods when the instruments are required to be operable.
3.
This instrumentation is excepted from the functional test definition. The functional test will censist of injecting a 4
simulated electrical signal into the measurement channel.
'(
These instrument channels will be calibrated using'pimulated i
electrical signals once every three months.
sp 4.
Simulated autcmatic actuation shall be performed once each operating cycle.
Where possibic, all logic system
{ '
functional tests will be performed using the test jacks.
~ -.
s 5.
Reactor low water level, high drywell pressure and high radiation main steam line tunnel are not included on Table 4.2-1 since they are tested on Table 4.1-2.
6.
The logic system functional tests shall include a calibration of time delay relays end timers necessary fo-proper functioning of the trip sys ems.
7.
At least one (1) Main Stack Dilution Fan is required to be in operation in order to isokinetically sampic the Main Stack.
Amendment No. yf,
, 57 85 1
6.
In cddition to itima 1, 2& 3 abova, two cdditional oparctore chall be rardily cynilable on cita wh nsvar the reactor is in other than cold chutdown.
During cold shutdown, an additionul operator shall be readily available on site.
j 7.
An individual qualified in radiation protection proce-dures shall be on site when fuel is in the reactor.
8.
In the event of illness or absenteeism up to two (2) hours is allowed to restore the shift crew or fire-brigade to normal complement.
9.
A Fire Brigade of fivo (5) or more members shall be maintained on site at I times.
This excludes two (2) members of the minimum sne.ru crew necessary for safe shutdown and any personnel required for other essential functions during a fire emergency.
10.
A Shift Technical Advisor shall be on site and readily available to the control room except during the cold shutdown or refuel mode.
6.3 PLANT-STAFF QUALIFICATIONS The minimum qualifications with regard to educational backg'round and experience for plant staff positions shown in Fig. 6.2-1 shall meet or exceed the minimum qualifications of ANSI NI8.1-1971 for comparable positions; except for the Radiation and Environmental Services Superintendent who shall meet or exceed the qualifications of, Regulatory Guide 1.8, September 1975 and the Shift Technic:al-Advisor who shall have a bachelor's degree or equivalent in a scientific or engineering discipline with specific training in plant design, and response and analysis of the plant for transients and accidents.
Any deviations will be justified to the NRC prior to an individual's filling of one of these positions.
6.4 RETRAINING AND REPLACEMENT TRAINING A training program shall be maintained under the direction of the Training Coordinator to assure overall proficiency of the plant staff organization.
It shall consist of both retraining and replacement training and shall meet or exceed the minimum requirements of Section 5.5 of ANSI NI8. 1-1971.
The retraining program shall not exceed periods two years in length with a curriculum designed to meet or exceed the requalification requirements of 10 CFR 55, Appendix A.
In addition fire brigade training shall meet or exceed the require-ments of NFPA 27-1975, except for Fire Brigade training sessions which -hall be held at least quarterly.
The effective date for implerxntation of fire brigade training is March 17, 1978.
6.5 REVIEW AND AUDIT Two seperate review groups for the review and audit of plant operations have been constituted.
One of these, the Plant Operating Review Committee (PORC), is an onsite group.
The other is an independent review and audit group, the offsite Safety Review Committee (SRC).
AmendmentNo.J,[,57 f
248
a PLANT OPERATING REVIEW COMMITT$E(PORC) 6. :'i.1 (A) ~ Membership The PORC is comprised of the Resident Manager (Chairman), Superintendent of Power jVice Chairman),
Operations Superintendent, Maintenan'ce Superintendent, Technical Services Superigtendenti Instrument and Control Sup'erintendent, Radiological and Environmental Services
' Superintendent and Reactor Analyst.
Special consultant to provide expert 4#vice may be utilized when the
. nature of a particular problem dictates.
l l
l Y.
Amendment No.,y(, 57 248a 4 i t u i
(B)
Alternates-Alternate members.shall~be appointed in writing by the
.PORC Chairman to serve on'a_ temporary basis; however, no more than two' alternates shall participate in PORC activit.ies at any one' time.
(C)
' Meeting Frequency Meetings will be_ called by the Chairman as the occasions for review or~ investigation arise.
Meetings will be no less
' frequent.than once a month.
4 (D)
Quorum The-Chairman-or.vice Chairman and four members, including designated alternates, shall constitute a quorum.
, E)
_ Responsibilities
(
1.
Review plant procedures, and changes thereto, re-quired by Specification 6.
2.
Review proposed tests and experi=ents that affect nuclear safety.
3.
Review proposed changes tO the Operating License and Technical Specifications.
4.
Review proposed changes or modifications to plant systems or equipment that ~ ffec. nuclear safety a
5.
Investigate violations of the Technical S'pecificationi and prepare and-forward a report covering evaluation and recc=mendatiens to prevent recurrence to the Resident Manager, who will forward the repcrt to the Manager - Nuclear Operations and to the Chairman of the Safety Review Ccmmittee.
6.
Review. plant operations to detect potential safety hazards.
7.
Review the Security Plan and implementing procedures annually.
249 Amendment No. g57
=..
1 3
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POWER hUTif0RITY OF TIIE STATE OF NEW YORK bn Aio[
JAMES A.
FITZPATRICK NUCLEAR POWER P LA':T
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PLANT STAFF ORGANI".ATION