ML20006D673
| ML20006D673 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 02/06/1990 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | GPU Nuclear Corp, Jersey Central Power & Light Co |
| Shared Package | |
| ML20006D674 | List: |
| References | |
| DPR-16-A-137 NUDOCS 9002140220 | |
| Download: ML20006D673 (11) | |
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UNITED STATES
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.8 NUCLEAR REGULATORY COMMISSION j
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GFU WUCLEAR. CORPORATION ME JERSEY. CENTRAL. POWER.8 LIGHT. COMPANY 00CKET WO.60-219 OYSTER CREEK NUCLEAR. GENERATING $TATION i
AMENDMENT T0. PROVISIONAL OPERATING. LICENSE J
l Amendment No.
137 1
License No. DPR-16 1.
The Nuclear Regulatory Comission (the Commission) has found that:
A.
The application for amendment by GPU Nuclear Corporation, et al.,
(thelicensee),datedJune 30, 1989 complies with the standards and l-requirements of the Atomic Energy Act of 1954, as amended (the Act),
and the Comission's rules and regulations set forth in 10 CFR Chapter I;-
l B.
The facility will operate in conformity with the application, L
the provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance (1) 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 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 Comission's regulations and all applicable regiirements have been satisfied.
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2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendant, and paragraph 2.C.(2) of Provisional Operating License No. DPR-16 is hereby amended to read as follows:
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(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.137, are here>y incorporated in the license. GPU Nuclear Corporation shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of issuance, to be implemented within 30 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
&k M
g John F. Stolz, Director Project Directorate 1-4 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: February 6, 1990
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ATTACfrENT Th t ICENSE AMENDHENT NO.137 PROVISIONAL OPERATING LICENSE NO. DPR-16 DOCKET NO. 50-219 Replar,e the following pages of the Appendix A Technical Specifications with the enclosed pages as indicated. The revised pages are identified by amendment nunber and contain vertical lines indicating the areas of change.
Remove Insert Page 3.13-3 Page 3.13-3 3.13-4 3.13-4 4.13-1 4.13-1 6-13 6-13 Table 3.13.1 Page 3.13-5 Table 3.13.1 Page 3.13-5 3.15.2 3.15-6 3.15.2 3.15-6 4.13.1 4.13-2 4.13.1 4.13-2 4.15.2 4.15-4 4.15.2 4.15-4 i
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2.
With the number of operable channels less than the total number of channels shown in Table 3.13.1, restore the inoperable channel to operable status within 30 days or place the reactor in the !.hutdown condition within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
3.
With the number of operable channels less than the minimum channels operable requirements of Table 3.13.1, restore at least one channel to operable status within 7 days or place the j
reactor in the shutdown condition within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
j G.
, Containment High-Range Radiation Monitor
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1.
Two in-containment high range radiation monitors shall be operable at all times except for cold shutdown and other times when primary containment is not required.
2.
In case of failure of one or more monitors, appropriate actions shall be taken to restore its operable capability as soon as possible.
Also, refer to Table 3.1.1 for any additional action which may be required.
3.
If the monitor or monitors are not restored to operable condition within 7 days after the failure, a special report shall be submitted to the NRC within 14 days following the
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event, outlining the cause of inoperability, actions taken and the planned schedule for restoring the equipment to operable status, j
H.
High Range Radioactive Noble Gas Effluent Monitor 1.
The high range radioactive noble gas effluent monitors 4
listed in Table 3.13.1 shall be OPERABLE during POWER OPERATION.
2.
With the number of OPERABLE channels less than required by the minimum channels OPERABLE requirements, restore the inoperable channel (s) to OPERABLE status within 7 days of the event or prepare and submit a Special Report within 30 days following the event outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the equipment to OPERABLE status.
BASES The purpose of the safety / relief valve accident monitoring instrumentation is to alert the operator to a stuck open safety / relief valve which could result in an inventory threatening event, j
As the safety valves present distinctly different concerns than those related to relief valves, the technical specifications are separated as to the actions taken upon inoperability. Clearly, the actuation of a safety valve will be immediately detectable by observed increase in drywell pressure.
Further confirmation can be gained by observing reactor pressure and water level. Operator
- action in response to these symptoms would be taken l
l Amendment No. : )4', JP/, %, id,13 7 OYSTER CREEK 3.13-3
l regardless of the acoustic monitoring system status. Acoustic monitors act only to confirm the reseating of the safety valve.
In actuality, the operator actions in response to the lifting of a safety valve will not change whether or not the safety valve reseats. Therefore, the actions taken for inoperable acoustic monitors on safety valves are significantly less stringent than that taken for those monitors associated with relief valves.
Should an acoustic monitor on a safety valve become inoperable, setpoints on adjacent monitors will be reduced to assure alarm actuation should the safety valve lift, since it is of no importance to the operator as to which valves lift but only that one has lifted. Analyses, using very conservative blowdown forces and attenuation factors, show that reducing the alarm setpoint on adjacent monitors to less than 1.4g will assure alarm actuation should the adjacent safety valve lift. Minimum blowdown force considered was 30g with a maximum attenuation of 27dB.
In actuality, a safety valve lift would result in considerably larger blowdown force.
The maximum attenuation of 27dB was determined based on actual testing of a similar monitoring system installed in a similar configuration.
The operability of the accident monitoring instrumentation ensures that sufficient information is available on selected plant parameters to monitor and assess these variables during and following an accident. This capability is consistent with NUREGs 0578 and 0737.
The capability is provided to detect and measure concentrations of noble gas fission products in plant gaseous effluents during and following an accident.
Two Radioactive Gaseous Effluent Monitoring Systems (RAGEMS) are installed at Oyster Creek to perform this function; one to monitor releases at the main stack (RAGEMS !) and one to monitor the turbine building vents (RAGEMS II).
These monitors augment the capabilities provided by the Post Accident Sampling System (see FSAR section 11.5) and the Offsite Thermoluminescent Dosimeter Program (see Emergency Plan section 7.5.2.2.b).
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OYSTER CREEK 3.13-4 Amendment No.: M', jW, S4', M13 7
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' 4.13 ACCIDENT MONITORING INSTRUMENTATION 5
Applicability:
Applies to surveillance requirements for the accident monitoring instrumentation, j
Objective:
To verify the operability of the accident monitoring instrumentation.
Specification:
A.
Safety & Relief Valve Position Indicators Each accident monitoring instrumentation channel shall be demonstrated operable by performance of the Channel Check and Channel Calibration operations at the frequencies shown in Table 4.13-1.
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B.
Wide Range Drywell Pressure Monitor i
Each accident monitoring instrumentation channel shall be demonstrated operable by performance of the Channel Check and Channel Calibration operations at the frequencies shown in Table 4.13-1.
C.
Wide Range Torus Water t.evel Monitor Each accident monitoring instrumentation channel shall I
be demonstrated operable by performance of the Channel Check and Channel Calibration operations at the frequencies shown in Table 4.13-1.
D.
Drywell H2 Moniter Each accident monitoring instrumentation channel shall i
be demonstrated operable by performance of the Channel Check and Channel Calibration operations at the frequencies shown in Table 4.13-1.
E.
Containment High-Range Radiation Monitor Each accident monitoring instrumentation channel shall be demonstrated operable by performance of the Channel Check and Channel Calibration operations at the frequencies shown in Table 4.13-1.
F.
High Range Radioactive Noble Gas Effluent Monitor Each accident monitoring instrumentation channel shall be demonstrated operable by performance of the Channel Check and Channel Calibration operations at the frequencies shown in Table 4.13-1.
Bases:
)
The operability of the accident monitoring instrumentation ensures that sufficient information is available on selected plant parameters to monitor and assess these variables during and following an accident.
This capability is consistent with hUREGs 0578 and 0737.
0YSTER CREEK 4.13-1 Amenament No.: 54',J4',IMI,137
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Special reporte shall be submitted to the appropriate arRC office within the time period specifled for each report. These reporte shall be submitted covering the activities identified below pursuant to the repiremente of the applicab'.e reference specification.
i statoriale Radiation surveillance specimen Reporte (4.34) s.
b.
Integrated Primary containment Leakage Teste (4.5) f Results of re w ired leak teste performed on sealed seuroes if the e.
teste reveal the presence of 0.005 mierecuries or more of removable contamination.
i, d.
2noperable Fire protection Spipment (3.13) core Spray Sparger Inservlee Insportion (Table 4.3.1-9) e.
j Prior to startup of each cycle, a special report presenting the results of the inservlee inoportion of the core Spray spargere during each refueling outage shall be submitted to the Ceamlesion for review.
I f.
Lipid radwaste batch dierharge escoeding specification 3.6.8.1.
Main condenser offgas discharge without treatment per Specification g.
3.6.D.1.
h.
Dese due to radioactive liquid effluent exceeding Specification 3.6.J.1.
t 1.
Air dose due to radioactive noble gas in gaseous effluent emeeeding specification 3.6.L.1.
Air dose due to radiodine and particulates exceeding Specification 3.6.H.1.
k.
Annual total dose due to radioactive effluente exceeding 8pecificatien 3.6.N.1.
1.
Records of results of analyses re p ired by the Radiological Environmental Monitoring Program.
Failures and challenges to Relief and Safety Valves 2.
Failures and challenges to Relief and Safety Valve which do not i
constitute an LER will be the subject of a special report submitted to the commiselon within 60 days of the occurrence. A challenge to defined as any automatic actuation (other than during surveillance or testing) of Safety or Relief Valves.
Plans for compliance with standby liquid control Specifications n.
3.2.C.3(b) and 3.2.C.3(e)(1) or plans to obtain enrichment test results per Specification 4.2.E.5.
Inoperable high range radioactive noble gas effluent monitor o.
(3.13.H)
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OYSTER CREEK 6-13 Amendment No.
6V, X 1 M, g g4 137 e,-
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TABLE 3.13.1 ACCIDENT MONITORING INSTRUMENTATION TOTAL NO. OF MINIMUM CHANNELS INSTRUMENT CHANNELS OPERABLE 1.
Relief Valve Position Indicator 1/ valve 1/ valve (Primary Detector *)
Reif ef Yalve Position Indicator 1/ valve (Backup Indications **)
2.
Wide Range Drywell Pressure 2
1 Monitor (PT/PR-53 4 54) 3.
Wide Range Torus Water Level 2
1 (LT/LR-37 & 38) 4.
Drywell H2 Monitor 2
i 5.
Containment High Range Radiation 2
1 r
6.
High Range Radioactive Noble Gas Effluent Monitor a.
Main Stack 1
1 b.
Turbine Building Vents 1
1 Acoustic Monitor Thermocouple Thermocouple TE 65A can be substituted for thermocouple TE210-43Y, W or X Thermocouple TE 65B can be substituted for thermocouple TE210-43Y or Z OYSTER CREEK 3.13-5 Amendment No.: 54',)T S8',94',M 13 7 o
A
? TA8tE 3.15.2 S
- =g RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRtBENTATION n
3 Minimum"
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Channels Essential Applicability Action Instrument Operable Function d
1.
Main Condenser Offgas Treatment System Recombiner 2
Monitor i,1 g..
c 125 Effluent Hydrogen Monitor concentration 2.
Stack Monitoring System a.
Radioactive Noble Gas Monitor (Iow range) 1 Monitor activity be 124 l concentration, alam b.
Iodine Sampler 1
Collect sample b,e 127 c.
Particulate Sampler 1
Collect sample b,e 127 d.
Effluent Flow Measuring Device 1
Measure air flow b
122 e.
Sampler Flow Measuring Device 1
Measure air flow b
128 y
h 3.
Turbine Building Ventilation Monitoring System e
a.
Radioactive Noble Gas Monitor (Iow range) 1 Monitor activity b
123 l.
concentration b.
Iodine Sampler 1
Collect sample b
127 l
c.
Particulate Sampler 1
Collect sample b
127 l
d.
Effluent Flow Measuring Device 1
Measure air flow b
122 e.
Sampler Flow Measuring Device 1
Measure air flow b
128 4.
Offgas Building Exhaust Ventilation Monitoring System y
a.
Radioactive Noble Gas Monitor 1
Monitor activity b
123 g
concentration g
b.
Iodine Sampler 1
Collect sample b
127 t
c.
Particulate Sampler 1
Co11ect sample b
127 d.
Sampler Flow Measuring Device 1
Measure air flow b
128 N:.
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TABLE 4013-1 j
ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS j
CHANNEL CHANNEL INSTRUMENT CHECK CALIBRATION
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1.
Primary and Safety Valve Position A
B Indicator (Primary Detector *)
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Relief and Safety Valve Position A
B l
Indicator (Backup Indications **)
J Relief Valve Position Indicator C
B (Consnon Header Temperature Element **)
i 2.
Wide Range Drywell Pressure Monitor A
D (PT/PR 53 8 54) 3.
Wide Range Torus Water Level Monitor A
D (LT/LR 37 4 38) 4.
Drywell H2 Monitor Al E
5.
Containment High Range Radiation A
F***
l Monitor 6.
High Range Radioactive Noble Gas Effluent Monitor a.
Main Stack A
F b.
Turbine Building Vent A
F
. Legend:
A = at least once per 31 days B = at least once per 18 months (550 days)
C = at least once per 15 days until channel celibration is performed and thence at least once per 31 days D = at least once per 6 months E = at least once per 12 months F = each refueling outage 1 = Span and Zero using calibration gases Acoustic Monitor Thermocouple I
Channel calibration shall consist of electronic signal substitution of I
the channel, not including the detector, for all decades above 10R/hr and a one point calibration check of the detector at or below 10R/hr by means of a calibrated portable radiation source traceable to NBS.
Amendment No* [88.,94',)f6,137 0YSTER CREEK 4.13-2
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o TABLE 4.15.2 v.
3 RAD 10 ACTIVE GASEOUS EFFLUENT ISIITORING INSTRt9ENTATION SURVEILLANCE REqulRElpTS 2
x Channel Channel Source Channel Functional Survetilaneg Instrument Check Check Calibration Test Required" 1.
Main Condenser Offges Treatment System 8
itydrogen Monitor D
N.A.
Q M
c 2.
Main Stack Monitoring System Radioactive Noble Gas Monitor (Lou Range) D M
R, Q'
b l
a.
b.
Iedine Sampler W
N.A.
N.A.
N.A.
b c.
Particulate Sampler W
N.A.
N.A.
N.A.
b d.
Effluent Flow Measuring Device D
N.A.
R Q
b
,a e.
Sampler Flow Measuring Device D
N.A.
R Q
b e-T 3.
Turbine Building Ventilation Monitoring System I
Radic:<tive Noble Gai, Monitor (Lou Range)
D M
R Q'
b l
a.
b.
Iodine Sampler W
N.A.
N.A.
N.A.
b c.
Particulate Sampler W
N.A.
N.A.
N.A.
b d.
Effluent flow Measuring Device D
N.A.
R Q
b
{
e.
Sampler Flow Measuring Device D
N.A.
R Q
b o
I 4.
Offgas Building Exhaust Ventilation 9
Monitoring System 7
a.
Radioactive Noble Gas Monitor D
M R
Q' b
I b.
Iedine Sampler Cartridge W
N.A.
N.A.
N.A.
b c.
Particulate Sampler y
N.A.
M.A.
N.A.
b d.
Sampler Flow Measuring Device D
N.A.
R N.A.
b L
U Legend 5 = once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> D = ence per 24 he m, W = one per 7 days, M = once per 31 days, Q = once per 92 days, SA = once per 184 days, R = once per 18 months, S/U = before each reactor start y,
P = completed before each release, N.A. = Not Appilcable.