ML20140A388
| ML20140A388 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 03/13/1986 |
| From: | Zwolinski J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20140A392 | List: |
| References | |
| TAC-62137, TAC-62138, NUDOCS 8603190416 | |
| Download: ML20140A388 (17) | |
Text
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g UNITED STATES p,
NUCLEAR REGULATORY COMMISSION 5
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NORTHERN STATES POWER COMPANY DOCKET NO. 50-263 MONTICELLO NilCLEAR GENERATING PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 39 License No. DPR-?2 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Northern States Power Company (the licensee) dated April 26, 1985, as supplemented on October 16, 1985, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and reoulations 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 Comission; 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 'reculations; 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, 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-2? is hereby amended to read as follows:
8603190416 860313 PDR ADOCK 05000263 P
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. 2 Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No. 39, 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.
FOR THE NUCLEAR REGULATORY COMMISSION
)
(,
John
. Zwolinski, Director BWR P ject Directorate #1 Division of BWR Licensina
Attachment:
Chanaes to the Technical Specifications Date of Issuance: March 13, 1986.
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ATTACHMENT TO LICENSE AMENDMENT NO. 39 FACILITY OPERATING LICENSE NO. DPR-22 DOCKET NO. 50-263 Revise Appendix "A" Technical Specifications by removing the pages identified below and inserting the attached pages. The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change.
REMOVE INSERT vi vi 61-61 129 129 130 130 130a 130b 131 131 132 132 132a 2291 2291 229n 2290 229q 229q 22.9r 229r 229s 229s 244 244 244a 244a 246b 246b
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LIST OF TABLES Table No.
3;g3 3.1.1 ' Reactor Protection System (Scram) Instrument Requirementa 28 4.1.1 Scram Instrument Functional Tests - Minimum Functional 32 Test Frequencies for Safety Instrumentation and Control Circuits 4.1.2 Scram Instrument Calibration - Minimum Calibration 34 Frequencies for Reactor Protection Instrument Channels 3.2.1 Instrumentation that Initiates Primary Containment 49 Isolation Functions 3.2.2 Instrumentation that Initistes Emergency Core Cooling Systema 52 3.2.3 Instrumentation that Initiates Rod Block 57 3.2.4 Instrumentation that Initiates Reactor Building Ventilation 59 Isolation and Standby Gas Treatment System Initiation 3.2.5 Instrumentation that Initiates a Recirculation Pump Trip 60 3.2.6 Instrumentation for Safeguards Bus Degraded Voltage and 60a Loss of Voltage Protection 3.2.7 Instrumcotation for Safety / Relief Valve Low-Low Set Logic 60b 3.2.8 other Instrumentation 60d 4.2.1 Minimum Test,s.ad Calibration Frequency for Core Cooling, Rod Block and Isolation Instrumentation 61 3.7.1 Primary Containment Isolation 172 3.8.1 Radioactive Liquid Effluent Monitoring Instrumentation 1891 3.8.2 Radioactive Gaseous Effluent Monitoring Instrumentation 198k 4.8.1 Radioactive Liquid Effluent Monitorir.g Instrumentation 198m Surveillance Requirements 4.8.2 Radioactive Gaseous Effluent Monitoring Instrumentation 198n Surveillance Requirements 4.8.3 Radioactive Liquid Waste Sampling and Analysis Program 198p 4.8.4 Radioactive Gaseous Waste Sampling and.*nalysis Program 198s 3.11.1 Maximum Average Planar Linear Heat Generation tate 215 vs. Exposure 1
3.13.1 Safety Related Tire Detection Instruments 227c vi Amendment 29, 30, 37, 39 t
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Tchle 4.2.I Minimum Test and Calibration Frequency For Core Cooling j'
Rod Block and Isolation Instrumentatian i
i Instrument Channel Test (3)
Calibration (3)
Sensor Check (3)
ECCS INSTRUMENTATION 4
j 1.
Reactor Low-Low Water Level (Note 7) once/ month Once/3 months Once/ Shift 1
2.
Drywell High Pressure (Nete 7) once/ month Once/3 months None j
3.
Reactor Low Pressure (Pump Start)
Note 1 Once/3 months None 4.
Reacter Low Pressure (Valve Permissive) Note 1 Once/3 months None 1
5.
Undervoltage Emergency Bus Refueling Outage Refueling Outage None
}
6.
Low Pressure Core Cooling Pumps Discharge Pressure Interlock Note 1 Once/3 months None I
7.
Loss of Auxiliary Power Refueling Outage Refueling Outage None j
8.
Condensate Storage Tank Level Refueling Outage Refueling Outage None 9.
Reactor High Water Level Once/ month Once/3 months Once/ day ROD BLOCKS I
1.
APRM Downscale Notes (1.5)
Once/3 months None j
2.
APRM Flow Variable Notes (1.5)
Once/3 months None 3.
IRM Upscale Notes (2,5)
Note 2 Note 2 4.
IRM Downscale Notes (2.5)
Note 2 Note 2 I
{
5.
RBM Upscale Onca/ronth Note (5)
Once/3 months None l
6.
RBM Downscale ones/ month Note (5)
Once/3 months None 7.
SRM Upscale Notes (2,5)
Note 2 Note 2 8.
SRM Detector not in Start-up Position Note 2 Note 2 Note 2 I
9.
Scram Discharge Volume-High Level Once/3 months Refueling outage None F
) f MAIN STEAM LINE ISOLATION
- s fI 1.
Steam Tunnel High Temperature Refueling Outage Refueling Outage None 2.
Steam Line High Flow Note 1 Once/3 months Once/ Shift
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D 3.2/4.2 61
o 3.0 LIMITING CONDITIONS FOR OPERATION 4.0 SURVEILI.ANCE REQUIREMENTS 3.
The dif fuser to lower plenum differential pressure reading on an individual jet pump is 10% or more, less than the mean of all jet pump differential pressures.
Except as permitted below, all safety The following surveillance requirements apply to related snubbers shall be operable all safety related snubbers.
l whenever the supported system is required to be Operable.
1.
Visual inspection of snubbera shall be conducted in accordance with the following 2.
Witli one or more snubbers made or found to schedule:
be inoperable for any reason when Operability is required, within 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />s:
No. of Snubbers Found Next Required Inoperable per Inspection Period a.
Replace or restore the inoperable snubbers Inspection Period l
to Operable status and perform an engineer-0 18 months 1 251 ing evaluation or inspection of the 1
12 months i 25%
supported components, or 2
6 months i 251 3,4 124 days 1 251 b.
Determine through engineering evaluation 5,6,7 62 days 1 251 that the as-found condition of the sr.ubber 8 or more 31 days 1 25%
had no adverse effect on the supported 4
components and that they would The required inspection interval shall not be retain their structural integrity in lengthened more than one step at a time.
the event of design basis seismic event, or Snubbers may be categorized in two groups,
" accessible" or " inaccessible" hased on their I
c.
Declare the supported system inoperable accessibility for inspection during reactbr and take the action required by the operation. These two groups may be inspected Technical Specifications for inoper-independently according to the above schedule.
l ability of that system.
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3.6/4.6 I29 Amendment No. 9, 39
l 3.0 LIMITING CONDITIONS FOR OPERATION 4.0 SURVEILLANCE REQUIREMENTS I
3.
All safety-related snubbers installed or 2.
Visual inspectionsshall verify (1) that there planned for use at Monticello are hydraulic are no visible indications of damage or snubbers. No mechanical snubbers are impaired operability and (2) attachments to l
used on safety-related systems at the supporting structure are secure.
Monticello.
If installed in the future.
Snubbers which appear inoperable as a result appropriate Technical Specifications changes of visual inspection may be determined Operable will be proposed within 60 days of for the purpose of establishing the next visual installation.
Inspection interval by:
a.
Clearly establishing the cause of the rejection for that particular snubber and for others that may be generically susceptible; and b.
Functionally testing the affected snobber in the as-found condition and finding it j
Operable per Specification 4.6.H.4.
However, when the fluid plunger gauge of a hydraulic snubber is below low range..the snubber shall be considered inoperable for the purposes of establishing the next visual inspection interval.
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l 3.6/4.6 130 Amendment No. 3, 9, 39
3.0 1,IMITING CONDITIONS FOR OPERATION 4.0 SURVEILI.ANCE REQUIREMENTS 3.
Functional testing of snubbers shall be conducted at least once per 18 months i 25%
during cold shutdown. Ten percent of the total number of each brand of snubber shall be functionally tested either in place or in a bench test.
For each snubber that does not meet the functional test acceptance criteria in Specification 4.6.H.4 below, an additional ten percent of that brand shall be functionally tested until no more failures are found or all anubbers of that brand have been tested.
The representative sample selected for
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functional testing shall include the varicus configurations, operating environments, and the range of size and capacity of the anubbers.
In addition to the regular sample and specified re-samples, snubbers which failed the previous fucctional test shall b'e retested during the
- r. ext test period if they were reinatalled as a safety-related snubber.
If a spare snubber has been installed in place of a failed safety related snubber, it shall be tested during the next period.
If any snubber selected for functional testing either fails to lockup or fails to move (i.e. frozen in place) the cause shall be evaluated and if caused by manufacturer or design deficiency, all snubbers of the some design subject to the same defect shall be functionally tested.
l 3.6/4.6 131 Amendment No. 9,39
t 3.0 LIMITING CONDITIONS FOR OPERATION 4.0 SURVEILI.ANCE REQUIREMENTS 4.
HyJraulic snubber functional tests shall verify t 'sa t :
e.
Activation (restraining action) is achieved within the specified range of velocity or acceleration in both tension and compression b.
Snubber bleed, or release rate, where required. l 1s within the specified range in compression or tension.
5.
For any snubbers found inoperable, an engineering evaluation or inspection shall be performed on the components which are supported by the snubbers. The purpose of this engineering evaluation or inspection shall be to determine if the components supported by the snubbers were adversely affected by the inopera-j bility of the snubbers in order to ensure that the supported component remains capable of meeting the designed service.
6.
The installation and maintenance records for each safety related snubber shall be reviewed at least l
4 once every 18 months to verify that the indicated service life will not be exceeded prior to the next scheduledsnubber service life review.
If the indicated service life will be exceeded, the snubber service life shall be re-evaluated or the snubber shall be replaced or reconditioned to extend I
Its service life beyond the date of the next j
scheduled service life review. This reevaluation, replacement, or reconditioning shall be indicated in the records.
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3.6/4.6 132 l
Amendment No. 9, 39
3.0 LIMITING CONDITIONS FOR OPERATION 4.0 SURVEILLANCE REQUIREMENTS 3.
Deviations are permittei from the required sampling schedule if saaples are unobtainable due to hazardous condicions, seasonable unavaila-bility, or to malfunction of automatic sampling equipment. If the latter occurs, every effort shall be made to complete corrective action prior to the end of the next sampling period.
4.
With the level of radioactivity in an environ-
=
mental sampling medium exceeding the reporting levels of Table 4.16.3 when averaged over any calendar quarter, in lieu of any other report, prepare and submit to the Commission within 30 days from the end of the affected calendar quarter a Report pursuant to Specification 6.7.C.3.
When more than one of the radionuclides in Table 4.16.3 are detected in the sampling medium, this report shall be submitted if:
concentration (1) + concentration (2) limit level (1) limit level (2)
When radionuclides other than those in Table 4.16-3 l
i are detected and are the result of plant effluents, this report shall be submitted if the potential annual dose to an individual is equal to or greater than the calendar year limits of Specifications 3.8.A.2. 3.8.B.2. or 3.8.'B.3.
This report is n'ot required if the measured level of radioactivity was i
not the result of plant effluents; however, in such
~an event, the condition shall be reported and described in the Annual Radiation Environmental Monitoring Report.
3.16/4.16 1
[
Amendment No. 15, $7,39 2291
Table 4.16.1 l
(Page 5 of 5)
MONTICEI.LO NUCI. EAR GENERATING PLANT RADIATION ENVIRONMENTAL MONITORING PROGRAM SAMPLE COLLECTION AND ANALYSIS Ilumber of Samples Exposure Pathway and Sampling and Type and Frequency and/or Sample Sample Locations **
Collection Frequency of Analysis c.
Food P' educts One sample of corn and At time of harvest Gamma Isotopic potatoes from any area analysis of edible j
that is irrigated by water portion of each in which liquid radioactive sample I
l effluent has been discharged.***
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j one sample of broad At time of harvest I-131 analysis leaf vegetation from of edible portion l
highest D/Q garden and of each sample i
one sample from 10-20 miles i
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00 Sample locations are given on the figure and table in the CDCM.
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As determined by methods outlined in the ODCM.
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3.16/4.16 j
I Amendment No. 15, 31, 39 229p i
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Table 4.16.2 (Page 1 of 2)
MAXIMUM VAttlES FOR Tile I.0WER LIMITS OF DETECTION (Lt.D)"'"
Airborne Particulate Water or Cag Fish Hilk Food Products Sediment Analysis (pC1/1)
(pci/m )
(pC1/kg, wet)
(pC1/1)
(pC1/kg, wet)
(pC1/kg, dry) gross beta 4
1 x 10~
b 3
2000(1000 )
H 54 15 130 Hn 59,
30 260 7
58, 60 1
0 Co 65,
30 260 7
-2 131 1
7x 10 1
60 f
7 b
-2 134,137,
15(10 ),
18 1 x 10 130 15 60 150 g
140 IS 15*
{
C Ba-La F
3.16/4.16 Amendment No. 13, 23, 31, 39 229q
^
TABI.E 4.16.2 (Page 2 of 2)
TABI.E NOTATION 3 - The LLD is the smallest concentration of radioactive material in a sample that will be detected with 95% probability with 5% probability of falsely concluding that a blank observation represents a "real" signal.
For a particular measurement system (which may include radiochemical separation):
=
E.V. 2.22. Y. exp(-Aa t) where LLD is the apriori lower limit of detection as defined above (as picoeurie per unit mass or volume),
I b is the standard deviation of the background counting rate or of the counting rate of a blank sample s
as appropriate (as counts per minute). Typical values of E V, Y and at shall be used in the calculations.
E is the counting efficiency (as counts per transformation)
V is the sample size (in units of mass or volume) 2.22 is the number of transformations per minute per picoeurie Y is the fraction radiochemical yield (when applicable)
A is the radioactive decay constant for the particular radionuclide At is the elapsed time between sample collection (or end of the sample collection period) and time of counting b - LLD for drinking water.
c - Total for parent and daughter, d - These LLDs apply only where "I-131 analysis" is specified.
e - Where " Gamma Isotopic Analysis" is specified, the LLD speciff' cations applies to the following radionuclides:
11-3, MN-54, Fe-59, Co-58, Co-60, Zn-65, Zr-Nb-95, Cs-134 Cs-137 and Ba-La-140.
Other peaks which are measurable and identifiable, together with the above nuclides shall be identified and reported.
3.16/4.16 229r Amendment No. 15, 31, 39
Table 4.16.3' REPORTING 1.EVELS FOR RADIDACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES
{
Reporting Levels i
i t
Airborne Particiclate Water or Cag Fish Milk Vegetables Analysis (pCi/1)
(pCi/m )
(pci/kg, wet)
(pC1/1)
(pCf/kg, wet) 11 - 3 2 x 10 (")
3 4
Mn-54 1x 10 3x 10 3
0 Fe-59 4x 10 1 x 10 0
3 Co-58 1x 10 3 x 10
.i i
2 4
Co-60 3x 10 1 x 10 t
2 4
Zn-65 3 x 10 2 x 10 Zr-Nb-95 4x 10 ( '}
I-131 2(")
0.9 3
1 x 10 3
3 Cs-134 30 10 1 x 10 60 1 x 10 Cs-137 50 20 2 x 10 70 2 x 10
..l Ba-La-140 2 x 10 (b) 3 x 10 (b) j 2
2 i
f a - For drinking water samples b - Total for parent and daughter c - If no drinking water pathways exist, a value of 20 pC1/1 may be used.
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3.16/4.16 l
Amendment No. 15, 31, 39 229s
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6.5 Plant Operating Procedures I
Detailed written procedures, including the applicable check-off lists and instructions, covering areas listed below shall be prepared and followed. These procedures and changes thereto, except as specified in 6.5.G shall be
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reviewed by the Operation; Committee and approved by a member of plant management designated by the Plant Manager.
i A.
Plant Operations 1.
Integrated and system procedures for normal startup, operation and shutdown of the reactor and all systems and components involving nuclear safety of the facility.
2.
Fuel handling operations.
3.
Actions to be taken to correct specific and foreseen potential or actual malfunction of systems or components including responses to alarms, primary system leaks and abnormal reactivity changes and including follow-up actions required after plant protective system actions have initiated.
4.
Surveillance and testing requirements that could have an effect on nuclear safety.
5.
Implementing procedures of the emergency plan. including procedures for coping with emergency conditions involving potential or actual releases of radioactivity.
6.
Implementing procedures of the fire protection program.
7.
Implementing procedures for the Process Control Program and Offsite Dose Calculation Manual including I
quality control measures.
Drills on the procedures specified in A.3 above shall be conducted as a part of the retraining program. Drills on the procedures specified in A.5 above shall be conducted at least semi-annually, including a check of communications l
with offsite support groups.
6.5 244 Amendment No. 15, 19, 25, 39 1
B. Radiological
- l. a. A Radiation Protection Program, consistent with the requirements of 10 CFR 20, shall be I
developed and followed. The Radiation Protection Program shall consist of the following:
(1) A Radiation Protection Plan, which shall be a complete definition of l
radiation protection policy and program (2) Procedures which implement the requirements of the Radiation Protection Plan i
The Radiation Protection Plan and implementing procedures, with the exception of those non-safety related procedures governing work activities exclusively applicable t.o 1
or performed by health physics personnel, shall be reviewed by the Operations Committee 3
and approved by a member of plant management designated by the Plant Manager. Ilealth physics procedures not reviewed by the Operations Committee shall be reviewed and app-roved by the Superintendent, Radiation Protection.
i
- b. Paragraph 20.203 " Caution signs, labels, signals and controls." In lieu of the " Control device" l
or alarm signal required by paragraph 20.203(c),(2), each high radiation area in which the intensity of radiation is 1000 mrem /hr or less shall be barricaded and conspicuously posted as I
a high radiation area and entrance thereto shall be controlled by requiring issuance of a l
Radiation Work Permit and any individual or group of individuals permitted to enter such areas I
shall be provided with a radiation monitoring device which continuously indicates the
)
radiation dose rate in the area.
J
- c. The above procedure shall also apply to each high radiation area in which the intensity of I
radiation is greater than 1000 mrem /hr, except that doors shall be locked or attended to l
prevent unauthorized entry into these areas and the keys or key devices for locked doors shall be maintained under the administrative control of the Plant Manager.
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6.5 244a 1
Amendment No. 19,39
E.
Offsite Dose Calculation Manual (ODCM)
The ODCM shall be approved by the Commission prior to initial implementation. Changes to the DDCM shall satisfy the following requirements:
l.
Shall be submitted to the Commission with the Semi-Annual Radioactive Effluent release report for the period in which the change (s) were made effective. This submittal shall contain:
a.
sufficiently detailed information to totally support the rationale for the change without benefit of additional or supplemental information. Information submitted should consist of a package of those pages of the ODCH to be changed with each page numbered and provided with a revision date, together with appropriate analyses or evaluations justifying the change (s).
b.
a determination that the change will not reduce the accuracy or reliability of dose calculations or setpoint determinations; and c.
documentation of the fact that the change has been reviewed an'd found acceptable by the Operations Committee.
2.
Shall become effective upon review and acceptance by the Operations Committee.
F.
Security Procedures shall be developed to implement the requirements of the Security Plan and the Security l
Contingency Plan. These implementing procedures, with the exception of those non-safety related procedures governing work activities exclusively applicable to or performed by security personnel, I
shall be reviewed by the Operations Committee and approved by a member of plant management I
designated by the Plant Manager. Security procedures not reviewed by the Operations Committee i
shall be reviewed and approved by the Superintendent. Security and Services.
G.
Temporary Changes to Procedures Temporary changes to those procedures which are required to be reviewed by the Operations Committee l
described in A, B, C, D, E and F above, which do not change the intent of the original procedures may be made with the concurrence of two individuals holding se'nior operator licenses. Such changes should be documented, reviewed by the Operations Committee and approved by a member of plant management designated by the Plant Manager within one month. Temporary changes to health physics and security procedures not reviewed by th'e Operations Committee shall be reviewed by the Superintendent, Radiation Protection for health physics procedures and the Superintendent, Security and Services for security procedures.
6.5 Amendment No. 15, 25, 39 246b
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