ML20079K908

From kanterella
Revision as of 23:17, 14 December 2024 by StriderTol (talk | contribs) (StriderTol Bot change)
(diff) ← Older revision | Latest revision (diff) | Newer revision → (diff)
Jump to navigation Jump to search
Proposed Tech Spec Changes,Providing Exception for Core Spray Sys Special Test
ML20079K908
Person / Time
Site: Brunswick  Duke Energy icon.png
Issue date: 01/06/1983
From:
CAROLINA POWER & LIGHT CO.
To:
Shared Package
ML20079K903 List:
References
NUDOCS 8301100215
Download: ML20079K908 (4)
v • d • e


Text

9 a

INDEX BASES SECTION PAGE 3/4.7 PIME SYSTEMS (Continued) 3/4.7.3 FLOOD PROTECTION..........................".............

B 3/4 7-1 3/4.7.4 REACTOR CORE ISOLAT. ION COOLING SYSTEM..................

B 3/4 7-1 3/4.7.5 llYDRAULIC SNUBBERS.....................................

B 3/4 7-2 3/4.7.6 SEALED SOURCE CONTAMINATION............................

B 3/4 7-3 3/4.7.7 FIRE SUPPRESSION SYSTEMS...............................

B 3/4 7-3 3/4.7.8 FIRE BARRIER PENETRATIONS..............................

B 3/4 7-4 3/4.8 ELECTRICAL POWER SYSTEMS..................................

B 3/4 8-1 3/4.9 REFUELING OPERATIONS 3/4.9.1 REACTOR MODE SW1TCH....................................

B 3/4 9-1 3/4.9.2 INSTRUMENTATION........................................

B 3/4 9-1 3/4.9.3 CONTROL ROD POS1 TION...................................

B 3/4 9-1 3/4.9.4 DECAY TIME.............................................

B 3/4 9-1 3/4.9.5 COMMUNICATIONS.........................................

B 3/4 9-1 3/4.9.6 CRANE AND HOIST OPERABILITY............................

B 3/4 9-2 3/4.9.7 CRANE TRAVEL-SPENT FUEL STORAGE P00L...................

B 3/4 9-2 4

3/4.9.8 WATER LEVEL-REACTOR VESSEL, and 3/4.9.9 WATER LEVEL-SPENT FUEL bTORAGE P00L....................

B 3/4 9-2 l

3/4.9.10 CONTROL ROD REM 0 VAL....................................

B 3/4 9-2 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 PRIMARY CONTAINMENT INTEGR1TY..........................

B 3/4 10-1 3/4.10.2 ROD SEQUENCE CONTROL SYSTEM............................

B 3/4 10-1 3/4 10.3 SilUTDOWN MARGIN DEMONSTRATIONS.........................

B 3/4 10-1 3/4.10.4 RECIRCULATION L00PS....................................

B 3/4 10-1 3/4.10.5 PLANT SERVICE WATER....................................

B 3/4 10-1 3/4.10.6 CORE SPRAY SYSTEM......................................

B 3/4 10-1 8301100215 630106 PDR ADOCK ObOOO324 P

PDR BRUNSWICK - UNIT 1 XII Amendment No.

a+

3/4.10 SPECIAL TEST EXCEPTIONS BASES 3/4.10.1 PRIMARY CONTAINMENT INTEGRITY-The requirements for PRIMARY CONTAINMENT INTEGRITY is-removed during the period when open vessel tests are being performed during low power PHYSICS TESTS.

3/4.10.2 ROD SEQUENCE CONTROL SYSTEM In order to perform the tests required in the Technical Specifications, it is necessary to bypass the sequence restraints on control rod movement.

The additional surveillance requirements ensure that the specifications on heat generation rates and shutdown margin requirements are not exceeded during the period when these tests are being performed.

3/4.10.3 SHUTDOWN MARGIN DEMONSTRATIONS Performance of shutdown margin demonstrations with the vessel head j

removed requires additional restrictions in order to ensure that. criticality does not occur.- These additional restrictions are specified in this LCO.

j 3/4.10.4 RECIRCULATIONS LOOPS This special test exception permits reactor criticality under no flow conditions and is required to perform certain start-up and PHYSICS TESTS while I

at low THERMAL POWER levels.

3/4.10.5 PLANT SERVICE WATER i

l This Special Test Exception permits securing the Service Water System conventional header when the nuclear header is out of service and is required to permit flange installation in service water system header cross-connect-piping.

3/4.10.6 CORE SPRAY SYSTEM This Special Test Exception permits the Core Spray System to be considered OPERABLE if the only reason the system would be declared inoperable is the inability to perform surveillance testing pursuant to Specification 4.5.3.1.c.1 due to the suppression chamber being drained.

BRUNSWICK - UNIT 1 B 3/4 10-1 Amendment No.

INDEX BASES SECTION PAGE 3/4.7 PLANT SYSTEMS (Continued) 3/4.7.3 FLOOD PROTECTION.......................................

B 3/4 7-1 3/4.7.4 REACTOR CORE ISOLATION COOLING SYSTEM..................

B 3/4 7-1 3/4.7.5 HYDRAULIC SNUBBERS.....................................

B 3/4 7-2 3/4.7.6 SEALED SOURC5 CONTAMINATION............................

B 3/4 7-3 3/4.7.7 FIRE SUPPRESSION SYSTEMS...............................

B 3/4 7-3 3/4.7.8 FIRE BARRIER PENETRATIONS..............................

B 3/4 7-4 3/4.8 ELECTRICAL POWER SYSTEMS..................................

B 3/4 8-1 3/4.9 REFUELING OPERATIONS 3/4.9.1 REACTOR MODE SWITCH....................................

B 3/4 9-1 3/4.9.2 INSTRUMENTATION........................................

B 3/4 9-1 3/4.9.3 CO NTRO L R0 D P0 S IT IO N...................................

B 3/4 9-1 3/4.9.4 DECAY TIME.............................................

B 3/4 9-1 3/4.9.5 COMMUNICATIONS.........................................

B 3/4 9-1 3/4.9.6 CRANE AND II0IST OPERABILITY............................

B 3/4 9-2 3/4.9.7 CRANE TRAVEL-SPENT FUEL STORAGE P00L...................

B 3/4 9-2 3/4.9.8 WATER LEVEL-REACTOR VESSEL, and 3/4.9.9 WATER LEVEL-SPENT FUEL STORAGE P00L....................

B 3/4 9-2 3/4.9.10 CONTROL ROD REM 0 VAL....................................

B 3/4 9-2 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 PRIMARY C0KEAINKENT INTEGRITY..........................

B 3/4 10-1 3/4.10.2 ROD SEQUENCE CONTROL SYSTEM............................

B 3/4 10-1 3/4 10.3 SilUTDOWN MARGIN DEMONSTRATIONS.........................

B 3/4 10-1 3/4.10.4 RECIRCULATION L00PS....................................

B 3/4 10-1 3/4.10.5 PLANT SERVICE WATER....................................

B 3/4 10-1 3/4.10.6 CORE SPRAY SYSTEM......................................

B 3/4 10-1 BRUNSWICK UNIT 2 XII Amendment No.

s

  • g 3/4.10 SPECIAL TEST EXCEPTIONS BASES 3/4.10.1 PRIMARY CONTAINMENT INTEGRITY The requirements for PRIMARY CONTAINMENT INTEGRITY is removed during the period when open vessel tests are being performed during low power PHYSICS TESTS.

3/4.10.2 ROD SEQUENCE CONTROL SYSTEM In order to perform the tests required in the Technical Specifications, it is necessary to bypass the sequence restraints on control rod movement.

The additional surveillance requirements ensure that the specifications on '

heat generation rates and shutdown margin requirements are not exceeded during the period when these testa are being performed.

3/4.10.3 SHUTDOWN MARGIN DEMONSTRATIONS Performance of shutdown margin demonstrations with the vessel head removed requires additional restrictions in order to ensure that criticality does not occur.

These additional restrictions are specified in this LCO.

I 3/4.10.4 RECIRCULATIONS LOOPS This special test exception permits reactor criticality under no flow conditions and is required to perform certain start-up and PHYSICS TESTS while at low THERMAL POWER levels.

3/4.10.5 PLANT SERVICE WATER This Special Test Exception permits securing the Service Water System conventional header when the nuclear header is out of service and is required to permit flange installation in service water system header cross-connect piping.

3/4.10.6 CORE SPRAY SYSTEM This Special Test Exception permits the Core Spray System to be considered OPERABLE if the only reason the system would be declared inoperable is the inability to perform surveillance testing pursuant to Specification 4.5.3.1.c.1 due to the suppression ch' mber being drained.

a BRUNSWICK - UNIT 2 B 3/4 10-1 Amendment No.

__

Retrieved from "https://kanterella.com/w/index.php?title=ML20079K908&oldid=4386555"