ML20151K833
| ML20151K833 | |
| Person / Time | |
|---|---|
| Site: | River Bend  |
| Issue date: | 05/13/1985 |
| From: | Bosnak R Office of Nuclear Reactor Regulation |
| To: | Crutchfield D Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20151K803 | List: |
| References | |
| FOIA-85-511 NUDOCS 8505230140 | |
| Download: ML20151K833 (5) | |
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.. ' i NUCLEAR REGULATORY COMMISSION g
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xf MAY 131935
! E.':07.A::.7:. F0F: Cecris t-:. Crutchfield, Assistar. Director Division o' Licensing TiCi':
Rcber-Besnak, Actine Assister.t Cirector fer Correnents and Structures Engineerire Divisien of Engineerine Ug) o g
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- FT OF TFE R:VER BEI Lc.'T 1 TECH::! CAL
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- 1. c..s.4 As recuested in yet.;r re:.o dated April 19,19EE, en above subject, we have revier:ac the River Eend Technical Specification 3.3.7.2 on Seistic Instru:-a-tation ar.c 3.7.10 en Structural Settleme-t. k'e find these Techr.ical Sceci'ica-icns, as written, are acceptable and no changes are recuired. A cocy of these Technical Soecifications is attached.
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. hY RobertBesnak,Adtined.ssistantDirector for Components ard structures Engineerir-Division of Engineering Er.cicsure: As stated
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_ INSTRUMENTATION r'm e SEISMIC MONITORING JNSTRUMENTATION Is it2 (
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LIMITING CONDITION FOR OPERATION 3.3.7.2 be OPERABL:{;.T e seismic monitoring instrumentation shown in Tabl e 3.3.7.2-1 shall APPLICABILITY: At all times.
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With one or more of the above required seismic mo it s.
incperaDie for more than 30 days, prepare and s b i oring instrum n
to the Commission pursuant to Specification 6 9 2 u m t a Special Report 10 cays outlining tne cause of the malfunction and the pl within the next restoring the instrument (s) to OPERABLE status ans for b.
The provisions of Specifications 3.0.3 and 3 0 4 are n t o applicable.
i SURVEILLANCE REOUIREMENTS 4.3.7.2.1 demonstrated OPERABLE by the performance of the t
TIONAL TEST and CHANNEL CALIBRATION operations at the Yr shall be CK, CHANNEL FUNC-Table 4.3.7.2-1.
equencies shown in
' 4.3.'7.2.2 during a seismic event greater than or equal to 0 01gE OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and a CHANNEL CAL uated following the seismic event.
and analyzed to determine the magnitude of the vibratory gro Report shall be prepared and submitted to the Commission tion 6.9.2 within 10 days describing the magnitude on. A Soecial pursuant to Specifica-resultant effect upon unit features important to safety, frequency spectru
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"'"',E SEISMIC MONITORING INSTRUMENTATIONlio/GPj[.'f MINIMUM INSTRUMENTS AND SENSOR LOCATIONS MEASUREMENT INSTRUMENTS
__ RANGE
~0PERABLE 1.
' Triaxial Time-History Accelerographs Reactor 81d; Mat EL 70'0" a.
b.
Reactor Bldg Ext Shield Wall 0 2 1. 0 g
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1 EL 232'0" Reactor Bldg Drpell EL 151'0" 0 2 1. 0 g c.
i c.
Free Field - Grade Level 0.1. 0 g 1
0 : 1. 0 g 1
2.
Triaxial Feak Acceleregraphs Reactor Bldg SLCS Stora a.
Reactor Bldg - RHR Inj.ge Tank 0 : 10.0 g b.
1 Piping 0: 10.0 g c.
Aux. Bldg Service Water Piping I
0 1 10.0 g 1
3.
Triaxial Seismic Switenes F.eactor 81dg Mat El 70'0"
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a.
0.025 to 0.25 g 1(*)
A.
Tria4tal Response-Spectrum Recorders i
Reactor 81dg Mat EL 70'0" a.
b.
Reactor 81dg Floor EL 141'0" 022g II ') ~
i Auxiliary Bldg Mat EL 70'0" 022g c.
1 Auxiliary Bldg Floor EL 141'0" 022g d.
1 022g-1
")With reactor control room indication and annunciation.
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L RIVER BEND - UNIT 1 3/4 3-71 19426 25 i
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... p b SE!!MIC MONITORING INSTRUMENTATION SURVEILLh.CE
<ss CHANNEL INSTRUMENTS AND SENSOR LOCATIONS CHANNEL FUNCTIONAL CHANNEL CHECK TEST
- CALIBRATION
- 1...Triaxthi Time-History Accelerographs Reactor Bldg. Mat EL 70'0" a.
M S A' -.
R b.
Reactor Bleg. Exit Shield Wall M
SA R
EL 232'0" Reactor Sleg. Dryvell EL 151'0" c.
M SA R
d.
Fre,e Field-Grade Level M
SA R
2.
Triaxial Peak Accelerographs Reactor Bldg. SLCS Stora a.
Reactor Bldg. - RHR Inj.ge Tank NA NA R
b.
Piping NA NA R
Aux. Eldg. Service Water Piping NA NA R
c.
3.
Triaxial Seismic Switches Reactor 81dg. Mat EL 70'0" a.
C M *)
SA R
4 Triaxial Response-Spectrum Recorders k
a.
Reactor 81dg. Mat EL 70'0' i
b.
Reactor Bldg. Floor EL 141'0" SA R
M NA c.
Auxiliary Bldg. Mat EL 70'0" SA R
NA NA R
d.
Auxiliary Bldg. Floor EL 141.0" NA NA R
(*)Except seismic trigger.
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RIVER BEND - UNIT 1 3/4 3-72
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PLANT SYSTEMS 3/4.7.10
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STRUCTURAL SETTLEMENT b
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LIMITING CONDITION FOR OPERATION 3.7.10 predicted values as showr. in Table 3.710-1 Structural s a
be within the Reactor Building a.
b.
Auxiliary Building Fuel Building
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d.
Control Building Diesel Generater Building e.
f.
Standby Cooling Tower, Basin and Pump House APPLICASILITY: At all times.
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With the measured structual settlement of any of th the Commission pursuant to Spe:ification 6 9 2 wit i
pecial Report to to demonstrate the co*ntinued structural integritya and plans to monitor the settlement of the affected structur ment, an analysis s
n the futu e.
a SURVEILLANCE REQUIREMENTS 4.7.10 demonstrated to be within the predicted settlementThe values:
ures shall be At least once per 92 days, using at least three mark a.
until there is essentially no movement during those 92 d b.
At least once per 24 months, using at least one ma k for at least 10 years.
r er per structure Basis Earthquake (OBE), using at least th c..
n Operational er structure.
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0Ia RIVER BEND - UNIT 1 3/4 7-34
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