ML20024G281
| ML20024G281 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 08/09/1977 |
| From: | NORTHERN STATES POWER CO. |
| To: | |
| Shared Package | |
| ML20024G278 | List: |
| References | |
| NUDOCS 9102080476 | |
| Download: ML20024G281 (6) | |
Text
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139' 3.7 and 4.7 Containment Systems og uw oo 139 A.
Primary Contairunent gg D FJ W 148 23 B.
Standby Cas Treatment System g
150 C.
Primary Contairunent Isolation valves 151-
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156 3.7 Bases 9
161 4.7 Bases 168 l
3.8 and 4.8 Radiation Environmental Monitoring Program 175 3.8 and 4.8 Bases 180 3.9 and 4.9 Auxiliary Electrical Systems 1
180 A.
Operational Requirements for Startup B.
Operational Regtairements for Continued Operation 181 O..
1.
Offsite Power (I.ine) 181 2.
Offsite Power (Transformers) 182 j
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'l LIST OF FIGURES
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Figure No.
Page No.
l 2.1-1 Deleted 2.3.1 APRM Flow Referenced Scram and Rod Block-Trip Settings 2.3.2 Relationship Between Peak liest Flux and Power for Peaking Factor of 3.08 12
. l 4.1.1
'N' Factor - Graphical Aid in the Selection of an Adequate Interval Between Tests 46~
4.2.1 System Unavailability 74 3.4.1 Sodium Pentaborate Solution Volume - Concentration Requirements 92 3.4.2 Sodium Pentaborate Solution Temperature Requirements 93 3.6.1 Change in Charpy V Transition Temperature versus Neutron Exposure 122 3.6.2 Minimum Temperature versus Pressure for Pressure Tests 122A 3.6.3 Minimus Temperature versus Pressure for Mechanical lleatup or Cooldown Following Nuclear Shutdown 122B jlll 3.6.4 Minimum Temperature versus Pressure for Core Operation 122C 4.6.1 Deleted 4.6.2 Chloride Stress Corrosion Test Results 8 500*F 123 l
4.8.1 Sampling Locations - Radiation Environmental Monitoring Program 173 3.II.1-A Maximum Average Linear lleat Generation Rate bersus Planar Average Exposure Hnnticello 8D219 Fuel 189H 3.11.1-8 Maximum Average Linear lleat Generation Rate versus Planar Average Exposure Monticello 7D230 Fuel 189I vii REV h
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LIST OF TABl.rg 3.1.1 Reactor Protection System (Scram) Instrument Requirements 30 4.1.1 Scram Instrument Functional fests - Minimum. Functional Test Frequencies for Safety Instrumentatica and ' Control Circuits
'34 4.1.2 Scram Instrument Calibrat.ien - Minimum Calibration Frequencies for Reactor Protection ' Instrument Channels 36 3.2.1 Instrumentation that Initiates Primary Containment Isolation Functions 50 3.2.2 instrumentation that Initiates Emergency Core tooling Systems 53 3.2.3 Instrumentation that Initiates Rod Block 57 3.2.4 Instrumentation that Initiates Reactor Building Ventilation Isolation and Standby Cas Treatment System Initiation 60 3.2.5 Trip Functions and Deviations 69 4.2.1 Minimum Test and Calibration Frequency For Core Cooling, Rod Block and Isolation Instrumentation 61 3.6.1 Safety Related Ilydraulic Snubbers 121B 4
4.6.1 In-Service Inspection Requirements for Monticello 124
,3.7.1 Primary Containment Isolation 153 4.8.1 Sample Collection and Analysis - Monticello Nuclear Generating Plant - Radiation Environmental Monitoring Program 169 6.5.1 Protection Factors for ".espirators 206 1x REV -
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Type of Sample
, Type of Analysis Collection Site Collection Frequency Aquatic Vegetation GS 1 Sample upstream of plant Semi-annually 1 Sample downstream of plant (when available) l l
l Fish (1 sample each GS 2 Samples upstream of plant Semi-annually of two game specie) 2 Samples downstream of plant (wben available, water
& ice conditions permit-ting) 137 Milk 131,
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1 Sample at the of fsite dairy Monthly 1
i farm having the highest X/Q 89,90Sr*
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1 mrem./yr 1 Sample from 10-20 mile location Tepsoil GS, 90Sr From the 7 air sampling locations, Once every 3 years aglg ar.d from 5 fields in the vicinity of the plant, including at least 2 fields irrigated with river water downstream of the plant.
l Natural GS, 131I 1 Sa=ple fran field having highest Semi-annually f
Vegetation X/Q (same as for milk) 1 Sample frm a field northwest of the plant (within 2 miles) 1 Sample feca 10-20 mile location (Same as for milk)
- Parformed only c. y/Q and Control Sa=ples 170 3.8/4.8 RE7
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DIS 1RIBUTION AFTER ISSUANCE OF OPERATING LICENSE NRC eo::u 196 p
u.s. Nucts An ns ouLAtonvguuisStoN DOCKsT NuM as:
a.n i V
W SO 2.43 NRC DISTRIBUTION ron PART 50 DOCKET MATERIAL TO.
FROM:
p4Ts or occL",sNT y
Northern States Power Company 8/0/77 j
Mr. Victor Stello Minneapolis, Minnesota L. O. Mayer o4Tsnecs'87th/77 CLsTTsa CNotomizso Pao'
'NPUT Pomu Nuussa or copias neceivso D o:isosN AL O vNc LAssiris o S"
3 ' &. i '@ ah 4
Ocorv ossenorioN sNcLosums 3
License No. DPR-22 Appl for knends tech specs proposed change concerning changes in the Radiation Environnental Monitoring Program...
j notorized 8/9/77......
(1.p)
(9.p)
PLANT NAME: Monticello RJL 8/17/77 SAFETY FOR ACTION /INFORMATION BRANCH CHIEF: (7)
D A U l.:5 i
l RAdo) A bone c D B A LL ADD INTERNAL DISTRIBUTION
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1 ICE (2) 7 OELD HANAUER l CHECK STELLO EISENHUT i
SHAO BAER BUTLER i
GRIMES I
J. COLLINS
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EXTERNAL OISTRIBUTION CONTROL NUMBER i
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11/AWSA/Y)L/.5 01M
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