ML20235C297

From kanterella
Jump to navigation Jump to search
Proposed Tech Specs Re MSIV Leakage Control Sys
ML20235C297
Person / Time
Site: Perry FirstEnergy icon.png
Issue date: 09/18/1987
From:
CLEVELAND ELECTRIC ILLUMINATING CO.
To:
Shared Package
ML20235C239 List:
References
NUDOCS 8709240410
Download: ML20235C297 (5)


Text

- _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ --

c -

CONTAINMENT SYSTEMS MSIV LEAKAGE CONTROL SYSTEM MITING CONDITION FOR ?.'/ERATION

\

/

3.6. 4 Two independent MSIV leakage control system (LCS) subsystems s 11 be OPERA E.

APPLICAB 4.ITY: OPERATIONAL CONDITIONS 1, 2, and 3.

ACTION:

With one MSIV akage control system subsystem inoperable, re ore the inoperable subs tem to OPERABLE status within 30 days or b in at least HOT SHUTDOWN within t next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN wit n the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. i SURVEILLANCE REQUIREM TS x <

4.6.1.4 Each MSIV leakag controlsystemsubsyste!shallbedemonstrated OPERABLE:

a. At least once per 31 ays by verify g:
1. Blower OPERABILITY y start g the blower (s) from the control room and operating t e blo r(s) for at least 15 minutes.
2. Inboard heater OPERABIL Y by demonstrating electrical continuity of the hea n element circuitry by verifying the inboard heater d ws 28 1 10% amperes per phase.
b. During each COLD SHUTD N, if not erformed within the previous 92 days, by cycling eacty motor operate valve, including the main steam stop valves, trough at least o .e complete cycle of full travel,
c. At least once r 18 months by:
1. Perfor nce of a functional test which cludes simulated actua on of the subsystem throughout its perating sequence, i and erifying that each automatic valve ac ates to its co ect position, and the blower (s) start (s).
2. erifying that the blower (s) develop (s) at leas the below required vacuum at the rated capacity:

a) Inboard system, 15" H2 O at 1 100 scfm.

b) Outboard system, 15" H2 O at 1 200 scfm.

d. By verifying the inboard flow and inboard and outboard pressur instrumentation to be OPERABLE by performance of a:
1. CHANNEL FUNCTIONAL TEST at least once per 31 days, and  ;
2. CHANNEL CALIBRATION at least once per 18 months. 1 PERRY - UNIT 1 3/4 6-8 g92404jO B7092e I p ADOCK 0500044o PDR

' CONT 5INMENTSYSTEMS BASES M .4 MSIV LEAKAGE CONTROL SYSTEM Calc W resulting from the maximum leakage nce for the main steam line isolatio ives in the postulated LOCA ions would be a small )

fraction of the 10 CFR 100 guide nes, provi e main steam line system from the isolation valves up to and ing the turbine condenser remains intact. Operating experiences dicate degradation has occasionally I occurred in the leak ti tee 3s of the MSIV's such the specified leakage requirements have always been maintained continuous . e requirement for  ;

the leaka rol system will reduce the untreated leakage fr MSIV's l whe ation of the primary system and containment is required.

3/4.6.1.5 CONTAINMENT STRUCTURAL INTEGRITY This limitation ensures that the structural integrity of the containment will be ma'intained comparable to the original design standards for the life of the unit. Structural integrity is required to ensure that the containment will withstand the maximum pressure of 15 psig in the event of a LOCA. A visual j inspection in conjunction with Type A leakage tests is sufficient to demonstrate 1 this capability.

3/4.6.1.6 CONTAINMENT INTERNAL PRESSURE The limitations on primary containment to secondary containment differen-tial pressure ensure that the primary containment peak pressure of 11.31 psig does not exceed the design pressure of 15.0 psig during LOCA conditions or that the external pressure differential does not exceed the design maximum external pressure differential of +0.8 psid. The limit of -0.1 to +1.0 psid for initial positive primary containment to secondary containment pressure will limit the primary containment pressure to 11.31 psid which is less than the design pres-sure and is consistent with the safety analysis.

3/4.6.1.7 CONTAINMENT [VERAGE AIR TEMPERATURE The limitation on containment average air temperature ensures that the containment peak air temperature does not excee~d the design temperature of 185*F during LOCA conditions and is consistent with the safety analysis.

3/4.6.1.8 DRYWELL AND CONTAINMENT PURGE SYSTEM The use of the drywell and cc stainment purge lines is restricted to the 42-inch outboard and 18-inch purra supply and exhaust isolation valves. These valves will close during a LOCA or steam line break accident and therefore the site boundary dose guidelines <>f 10 CFR Part 100 would not be exceeded in the event of an accident during purging operations. The term sealed closed as used in this context means that the valve is secured in its closed position l

by deactivating the valve motor operator, and does not pertain to injecting seal l water between the isolation valves by a seal water system.

l l

PERRY - UNIT 1 B 3/4 6-2

(

j- CONTAINMENT SYSTEMS

! PRIMARY CONTAINMENT LEAKAGE i LIMITING CONDITION FOR OPERATION 3.6.1.2 Primary containment leakage rates shall be limited to:

a. An overall integrated leakage rate of less than or equal to 0.75 L,,

0.20 percent by weight of the primary containment air per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at P,, 11.31 psig.

b. for all A combined leakage penetrations rate of except and all valves, less than for or equal main to 0.60 steam line L, isolation valves and valves which are hydrostatically leak tested per Table 3.6.4-1, subject to Type B and C tests when pressurized to P,, 11.31 psig.

c.

/00 a//

Less than or equal to FJ scf per hour for =y := main steam lines ^

through tha isolation valves when tested at P,, 11.31 psig.

d. A combined leakage rate of less than or equal to 0.0504 L for all penetrations shown in Table 3.6.4-1 of Specification 3.6.4 as secondary containment bypass leakage paths when pressurized in accorcance with Table 3.6.4-1.
e. A combined leakage rate of less than or equal to 1 gpm times the total number-of containment isolation valves in hydrostatically tested lines per Table 3.6.4-1 which penetrate the primary containment, when tested at 1.10 P,, 12.44 psig.

APPLICABILITY: OPERATIONAL CONDITIONS 1, 2* and 3.

ACTION:

With:

a. The measured overall integrated primary containment leakage rate exceeding 0.75 L,, or
b. The measured combined leakage rate for all penetrations and all valves except for main steam line isolation valves and valves which are hydrostatically leak tested per Table 3.6.4-1, subject to Type B and C tests exceeding 0.60 L,, or The measured leakage rate exceeding too,26'scf per hour fora/any/
c. en:

main steam lineSthrough the isolation valves, or A

d. The combined leakage rate for all penetrations shown in Table 3.6.4-1 as secondary containment bypass leakage paths exceeding 0.0504 L,, or
e. The measured combined leakage rate for all containment isolation valves in hydrostatically tested lines per Table 3.6.4-1 which pene-trate the primary containment exceeding 1 gpm times the total number of such valves:

"See Special Test Exception 3.10.1.

PERRY - UNIT 1 3/4 6-3

CONTAINMENT SYSTEMS LIMITING CONDITION FOR OPERATION (Continued)

ACTION (Continued) restore:

a. The overall integrated leakage rate (s) to less than or equal to 0.75 L,, and
b. The combined leakage rate for all penetrations and all valves except for main steam line isolation valves and valves which are hydrostati-cally leak tested per Table 3.6.4-1, subject to Type B and C tests to less than or equal to 0.60 L,, and

/00 g1

c. The leakage rate to less than JEscf per hour for ry/f= main steam linesthrough the isolation valves, and A
d. The combined leakage rate for all penetrations shown in Table 3.6.4-1 as secondary containment bypass leakage paths to less than or equal to 0.0504 L,, and
e. The combined leakage rate for all containment isolation valves in hydrostatically tested lines per Table 3.6.4-1 which penetrate the primary containment to less than or equal to 1 gpm times the total number of such valves, prior to increasing reactor coolant system temperature above 200 F.

SURVEILLANCE REQUIREMENTS 4.6.1.2 The primary containment leakage rates shall be demonstrated at the following test schedule and shall be determined in conformance with the cri-teria specified in Appendix J of 10 CFR Part 50 using the methods and provi-sions of ANSI N45.4-1972 and BN-TOP-1; test results shall also be reported '

based on the Mass Point Methodology described in ANSI /ANS N56.8-1981:

a. Three Type A Overall Integrated Containment Leakage Rate tests shall be conducted at 40 + 10 month intervals during shutdown at P ,

11.31 psig during each 10 year service period. Thethirdteltof each set shall be conducted during the shutdown for the 10 year plant inservice inspection.

b. If any periodic Type A test fails to meet 0.75 L , the test schedule I forsubsequentTypeAtestsshallbereviewedan8approvedbythe Commission. If two consecutive Type A tests fail to meet 0.75 L Type A test shall be performed at least every 18 months until tw8, a consecutive Type A tests meet 0.75 L,, at which time the above test schedule may be resumed.
c. The accuracy of each Type A test shall be verified by a supplemental test which: v- !n 10),<_.'

l PERRY - UNIT 1 3/4 6-4 L_--_--____-__--

I 1

l i

f I

'Of a y E d3S L0b!

S0-08Nsg l