ML20085K459

From kanterella
Revision as of 14:30, 16 April 2020 by StriderTol (talk | contribs) (StriderTol Bot insert)
(diff) ← Older revision | Latest revision (diff) | Newer revision → (diff)
Jump to navigation Jump to search
Proposed TS 3/4.6.2, Depressurization & Cooling Sys, Changing Required Test Frequency for Reactor Bldg Spray Nozzle Flow Test from Once Per Five Yrs to Once Per Ten Yrs
ML20085K459
Person / Time
Site: Summer South Carolina Electric & Gas Company icon.png
Issue date: 06/19/1995
From:
SOUTH CAROLINA ELECTRIC & GAS CO.
To:
Shared Package
ML20085K456 List:
References
NUDOCS 9506230382
Download: ML20085K459 (5)
v • d • e


Text

DocumentControl Desk AttachmentI TSP 950006 RC-95-0162 Page 1 of1 SCE&G -- Explanation of Changes PAGE ted Br Description of Change Reason for Change AIfc*ti9n g

3/4 6-12 4.6.2.1.d 1 Change "5" years to "10" years. To incorporate one of the Technical Specification improvement initiatives of NUREG 1431(MERITS), NUREG 1366, ,

and Generic Letter 93 05.

l l

l l

I ph[ hoo! ((

P

CONTAINMENT SYSTEMS 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS REACTOR BUILDING SPRAY SYSTEM LIMITING CONDITION FOR OPERATION 3.6.2.1 Two independent reactor building spray systems shall be OPERABLE with each spray system capable of taking suction from the RWST and automatically transferring suction to the spray sump.

APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION:

With one reactor building spray system inoperablu, restore the inoperable spray system to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />; restore the inoperable spray system to OPERABLE status within the next 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

SURVEILLANCE REQUIREMENTS l

I 4.6.2.1 Each reactor building spray system shall be demonstrated OPERABLE:

a. At least once per 31 days by verifying that each valve (manual, power operated or automatic) in the flow path that is not locked, sealed, or otherwise secured in position, is in its correct position.
b. By verifying, that on recirculation flow, each pump develops a' discharge pressure of greater than or equal to 195 psig when tested pursuant to Specification 4.0.5,
c. At least once per 18 months during shutdown, by:
1. Verifying that each automatic valve in the flow path actuates to its correct position on each of the following test signals a l

Phase ' A', Reactor Building Spray Actuation, and Containment Sump Recirculation.

2. Verifying that each spray pump starts automatically on a Reactor Building Spray Actuation test signal,
d. At least once per ' years by performing an air or smoke or equivalent l flow test through each spray header and verifying each spray nozzle is unobstructed.

f SUMMER - UNIT 1 3/4 6-12

CONTAINMENT SYSTEMS ,

3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS - 1 E

LIMITING CONDITION FOR OPERATION 3.6.2.1 Two independent reactor building spray systems shall be OPERABLE with .

each spray system capable of taking suction from the RWST and automatically ,

transferring suction to the spray pump.  ;

APPLICABILITY: MODES 1,2,3, and 4.

ACTION:

With one reactor building spray system inoperable restore the inoperable spray system to OPERABLE status within 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />,s or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />; restore the inoperable spray system to OPERABLE  !

status within the next 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in COLD SHUTDOWN within the followmg 1 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />. '

SURVEILLANCE REQUIREMENTS i

4.6.2.1 Each reactor building spray system shall be demonstrated OPERABLE:

a. At least once per 31 days by verifying that each valve (manual, I'

power operated or automatic) in the flow path that is not locked, sealed, or otherwise secured in position, is in its correct position.

b. By verifying, that on recirculation flow, each pump develops a discharge pressure of greater than or equal to 195 psig when tested pursuant to Specification 4.0.5. )
c. At least once per 18 months during shutdown, by:
1. Verifying that each automatic valve in the flow path actuates to its correct position on each of the following test signals a Phase 'A', Reactor Building Spray Actuation, and Containment Sump i Recirculation 4
2. Verifying that each spr,ay pump starts automatically on a Reactor Building Spray Actuation test signal.
d. At least once per 10 years by performing an air or smoke or equivalent l ,

flow test through each spray header and verifying each spray nozzle is unobstructe<..

SUMMER - UNIT 1 3/4 6-12 Amendment No.

L

m . . . . . . _ . . .

y

. .. . w .

Document Control Desk

-  : , AttachmentII  :

[ TSP 950006

~

RC-95-0162

- Page 1 ofi .l SAFETY EVALUATION -

U .'FOR REVISING THE SPECIFICATION FOR-DEPRESSURIZATION AND COOLING SYSTEMS IN THE VIRGIL C.' SUMMER' NUCLEAR STATION 1 TECHNICAL SPECIFICATIONS

Description of Amendment Reauest The Virgil C. Summer Nuclear Station (VCSNS) Technical Specifications (TS) 3/4.6.2, Depressurization and Cooling Systems, is being revised to change the required test frequency for reactor building spray nozzle flow test from the current  ;

once per five years to once per ten years. This proposed technical specification change request (TSCR) has previously been reviewed and approved by the NRC and generically recommended for nuclear plants as part of technical specification improvement initiatives in NUREG 1431 (MERITS), NUREG 1366, and Generic Letter (GL) 93-05.' Similar requests have been submitted to the NRC by Florida - -

Power and Light (April 19,1993) and Virginia Power (February 25,1994).

j Safety Evaluation ,

a This TSCR will not have a detrimental effect on the level of safety provided by the reactor building spray system. The reactor building spray system is composed of 304 i stainless steel, which is resistant to corrosion which could result in clogging of the spray nozzles. The reactor building spray system is normally idle, with the exception -

of testing, and is therefore not readily subject to the intrusion of foreign materials.

The design of VCSNS reactor building spray system as discussed in the FSAR does I require periodic testing, but does not specify the frequency for the tests. i i

Industry wide spray system reliability, as demonstrated by the performance of these tests, justifies this change in the frequency of the nozzle flow test.

o l

l

.l u

I l

a

m. f j Document Contr:1 Desk ,

4 AttachmentHI  !

l TSP 950006 i H

RC-95-0162 s :Page l of1 SIGNIFICANT HAZARDS EVALUATION FOR REVISING THE SPECIFICATION FOR DEPRESSURIZATION AND COOLINGSYSTEMSIN THE VIRGIL C. SUMMER NUCLEAR STATION TECHNICAL SPECIFICATIONS ,

l Description of AmendmentReauest The Virgil C. Summer Nuclear Station (VCSNS) Technical Specifications (TS) 3/4.6.2, Jepressurization and Cooling Systems, is being revised to change the required test frequency for reactor buildinf spray nozz. e flow test from the current once per five years to once per ten years. T us proposed technical specification change  ;

F request (TSCR) has previously been reviewed and approved by the NRC and .

generically recommended for nuclear plants as part of technical specification improvement initiatives in NUREG 1431 (MERITS), NUREG 1366, and Generic Letter (GL) 93-05. Similar requests have been submitted to the NRC by Florida  !

Power and Light (April 19,1993) and Virginia Power (February 25,1994). (

Basis for No Significant Hazards Consideration Determination South Carolina Electric & Gas Company (SCE&G) has evaluated the pro changes to the VCSNS TS described above against the Significant H s Criteria of10 CFR 50.S2 and has determined that the changes do not involve any significant f" hazard for the following reasons:

'1. The probability or consequences of an accident previously evaluated is not  :

significantlyincreased. l This change does not effect the probability or consequences of an accident. The Reactor Building Spray System is normally idle, with the exception of testing.

The possibility of the introduction of foreign material or corrosion products to restrict flow is minimized because of the use of 304 stainless steel as construction material. This change results in an extension of the testing periodicity only.

2. The possibility of an accident or a malfunction of a different type than any previously evaluated is not created.'

This change results in an extension of the testing periodicity only and does not result in an accident not previously evaluated.

3. The margin of safety has not been significantly reduced.

The Reactor Building Spray Sptem is normally idle, with the exception of testing. The possibility of the introduction of foreign material or corrosion

, products to restrict flow is minimized because of the use of 304 stainless steel as construction material. Industry wide spray system reliability, as demonstrated by the performance of these tests, justifies this change in the frequency of the nozzle flow test. This results in an extension of the testing periodicity only and  ;

will not significantly reduce a margin of safety.

,,. _ _ - ._ _ _ _ _.

Retrieved from "https://kanterella.com/w/index.php?title=ML20085K459&oldid=2738759"