ML20215E291
| ML20215E291 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon, 05000000 |
| Issue date: | 06/11/1985 |
| From: | Kirsch D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | Thompson H Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20215E267 | List: |
| References | |
| FOIA-86-197 TAC-59010, NUDOCS 8610150202 | |
| Download: ML20215E291 (7) | |
Text
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UNITED STATE 3 y ) 3.,,(f( p, NUCLEAR REGULATORY COMMISSION
-( ^^i#/
E REGION V
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o 1450 MARIA LANE, SUITE 210
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,o WALNUT CREE K, CALIFoRNI A 94596
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JUN 111985 MEMORANDUM FOR: Hugh L. Thompson, Jr., Director Division of Licensing FROM:
Dennis F. Kirsch, Acting Director Division of Reactor Safety and Projects
SUBJECT:
REQUEST FOR TRANSFER OF RESPONSIBILITY FOR EVALUATION OF APPLICABILITY OF SUBSECTION IWV-3427 0F ASME CODE, SECTION XI AT DIABLO CANYON During an inspection of inservice testing (IST) of pumps and valves at Diablo Canyon Unit I, it was identified that leakage tests for Reactor Coolant System pressure isolation valves did not determine actual leakage rates and thus leakage rates were not being trended. As 14 of these 18 valves are at least 6 inches in diameter, subsection IWV-3427 to ASME Code,Section XI requires trending of leakage rates to establish the need for increase testing frequency or corrective action. These valves are only being tested per specifications 4.0.5 and 4.4.6.2.2 of the technical specifications, a copy of applicable portions is enclosed, to determine that leakage is less than one gallon per minute.
Region V request NRR to assume lead responsibility for technical evaluation of the licensee's position, that actual leakage rates for the subject valves and trending of same are not required.
Please contact C. Clark (FTS 463-3741), if additional information is required I
regarding this request.
l Dennis F. Kirsch, Acting Director Division of Reactor Safety and Projects
Enclosures:
NUREC-1102, Cover Page, Pages 3/4 0-2, 3/4 0-3, 3/4 4-19, 3/4 4-20, 3/4 4-21 M. Mendonca, SRI, Diablo Canyon R. Dodds, RV T. Young, RV J. Burdoin, RV C. Clark, RV 861003 er,#1,,
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.ggyqE,tUW.ORlW ME COM, I
NUREG-1102 J0 X0~ H OVE Technical Specifications i j
Diablo Canyon l\\ uclear Power P ant, j
Unit \\lo.1 Docket No. 50-275 i
Appendix "A" to I
License No. DPR-80 t
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issued by the U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation November 1984 k N, n
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APP'LICABILITY i
SURVEILLANCE REQUIREMENTS i
4.0.1 Surveillance Requirements shall be met during the OPERATION 5L MODES or other conditions specified for individual Limiting Conditions for Operation unless otherwise stated in an individual Surveillance Requirement. -
7.
4.0.2 Each Surveillance Requirement shall be performed within the specified 1
time interval with:
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A maximum allowable extension not to exceed 25% of the surveillance a.
interval, but b.
The combined time interval for any 3 consecutive surveillance intervals shall not exceed 3.25 times.the specified surveillance interval.
4.0.3 Failure to perform a Surveillance Requirement within the specified time interval shall constitute a failure to meet the OPERABILITY requirements for a Limiting Condition for Operation.
in the individual Specifications.
Exceptions to these requirements are stated performed on inoperable equipment. Surveillance requirements do not have to be 4.0.4 Entry into an OPERATIONAL MODE or.other specified condition shall not be made unless the Surveillance Requirement (s) associated with the Limiting Condition for Operation have been performed within the stated surveillance interval or as otherwise specified.
4.0.5 Code Class 1, 2 and 3 components shall be applicable as fol' lows: S Inservice inspection of ASME Code Class 1, 2 and 3 components and a.
inservice testino of ASME Code Class 1, 2 and 3 pumps and valves shall
_tg performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and aDDlicable Addenda as required by 10 CFR 50, Section 50.55a(g), except where specific written relief has been
~_ granted by the Commission pursuant to 10 CFR 50, Section 50.55a(g)(6)(i).
b.
Surveillance intervals specified in Section kl of the ASME Boiler and Pressure Vessel Code and applicable Addenda for the inservice j
inspection and testing activities required by the ASME Boiler and Pressure Vessel Code and applicable Addenda shall be applicable as follows in these Technical Specifications:
ASME Boiler and Pressure Vessel Code and applicable Addenda Required frequencies for terminology for inservice performing inservice inspection and testing activities inspection and testing activities Weekly e
Monthly At least once per.7 days Quarterly or every 3 months At least once per 31 days Semiannually or every 6 months At least once per 92 days Every 9 months At least once per 184 days Yearly or annually At least once per 276 days f
l At least once per 366 days I
DIABLO CANYON - UNIT 1 3/4 0-2
APPLICABILITY 1
SURVEILLANCE REQUIREMENTS (Continued) 4.0.5 (Continued) 7
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The provisions of Sp_ecif.ication 4.0.2 are applicable to the above c.
required frequencies for performing inservice inspection and testing activities.
d.
Performance of the above inservice inspection and testing activities shall be in addition to other specified Surveillance Requirements.
l Nothing in the ASME Boiler and Pressure Vessel Code shall be construed e.
to supersede the requirements of any Technical Specification.
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DIABLO CANYON - UNIT 1 3/4 0-3
- ' REACTOR COOLANT SYSTEM OPERATIONAL LEAKAGE LIMITING CONDITIONS FOR OPERATION 3.4.6.2 Reactor Coolant System lea'kage shall be limited to:
No PRESSURE BOUNDARY. LEA'KAGE, a.
b.
I gpm UNIDENTIFIED LEAKAGE, I gpm total primary-to-secondary leakage through all steam generators c.
and 500 gallons per day through any one steam generator, d.
10 gpm IDENTIFIED LEAKAGE fr6m the Reactor Coolant System, 40 gpm CONTROLLED LEAKAGE at a Reactor Coolant System pressure of e.
2230 i'20 psig, and-7 f.
I gpm leakage at a Reactor Coolant System pressure of 2235 20 psig 4
from any Reactor Coolant System pressure isolation valve specified
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in Table 3.4-1.
APPLICABILITY:
MODES 1, 2, 3 and 4.
ACTION:
With any PRESSURE BOUNDARY LEAKAGE, be in at least HOT STANDBY a.
within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and 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 />.
b.
With any Reactor Coolant System leakage greater than any one of the above limits, excluding PRESSURE BOUNDARY LEAKAGE and leakage from Reactor Coolant System pressure isolation valves, reduce the leakage rate to within limits within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 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 /> and 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 />.
With any Reactor Coolant System pressure isolation valve leakage c.
greater than the above limit, isolate the high pressure portion of the affected system from the low pressure portion within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by use of at least two closed manual and/or deactivated automatic valves, cr 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 /> and in COLD SHUIDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
I DIABLO CANYON - UNIT 1 3/4 4-19
REKCTOR COOLANT SYSTEM s
SURVEILLANCE REQUIREMENTS
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4.4.6.2.1 Reactor Coolant System leakages sha'll be demonstrated tolbe within each of the above limits by:
a.'
Monitoring the containment atmosphere particulate or gaseous radioactivity monitor at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, b.
Monitoring the containment structure sump inventory and discharge at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, c.
Measurement of the CONTROLLED LEAKAGE to the reactor coolant pump seals at least once per 31 days when the Reactor Coolant System pressure is 2230 1 20 psig with the modulating valve fully open.
The provisions of Specification 4.0.4 are not applicable for entry into MODE 3 or 4, d.
Performance of a Reactor Coolant System water inventory balance at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, except when T,yg is being changed by greater than 5*F/ hour or when diverting reactor coolant to the liquid holdup tank, in which cases the required inventory balance shall be performed within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after completion of the excepted operation, and e.
Monitoring the reactor head flange leakoff system at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
4.4.6.2.2 Each Reactor Coolant System pressure isolation valve specified in Table 3.4-1 shall be demonstrated OPERABLE pursuant to Specification 4.0.5,
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except that in lieu of any leakage testing required by Specification 4.0.5,
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each valve shall be demonstrated OPERABLE by verifying leakage to be within its limit:
i a.
Every refueling outage during startup, b.
Prior to returning the valve to service following maintenance, repair or replacement work on the valve, and c.
Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> following valve actuation due to automatic or manual action or flow through the valve. After each disturbance of the valve, in lieu of measuring leak rate, leak-tight integrity may be verified by absence of pressure buildup in the test line downstream of the valve.
The provisions of Specification 4.0.4 are not applicable for entry into MODE 3 or 4.
DIABLO CANYON - UNIT 1 3/4 4-20 e.
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TABLE 3.4-1 REACTORCOOLANTSYSTENPRESSUREISblATIONVALVES VALVE NUMBER
_ FUNCTION a.
8948 A, B, C, and D.
=
first off check valves from RCS cold legs b.
8819 A, B, C, and D SIS second off check valves from RCS cold legs c.
8818 A, B, C, and D RHR second off check valves from RCS cold legs d.
8956 A, B, C,'and D.
Accumulator second off check valves from RCS cold legs e.
8701* and 8702*
RHR suction isolation valves
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" Testing per Specification 4.4.6.2.2c. not required.
DIABLO CANYON - UNIT 1 3/4 4-21
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