ML20197K155
| ML20197K155 | |
| Person / Time | |
|---|---|
| Site: | 05000000, Diablo Canyon |
| Issue date: | 08/09/1985 |
| From: | Bosnak R Office of Nuclear Reactor Regulation |
| To: | Novak T Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML082840462 | List:
|
| References | |
| FOIA-86-197 NUDOCS 8508160097 | |
| Download: ML20197K155 (5) | |
Text
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UNITED STATES o
NUCLEAR REGULATORY COMMISSION 5
j WASHINGTON, D. C. 20555
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Docket No.: 50-275 and 50-323 MEMORANDUM FOR: Thomas M. Novak, Assistant Director for Licensing Division of Licensing FROM:
Robert J. Bosnak, Acting Assistant Director for Components and Structures Engineering Division of Engineering
SUBJECT:
DIABLO CANYON TECHNICAL SPECIFICATIONS - PRESSURE ISOLATION VALVE LEAKAGE TESTING The pressure isolation valve (PIV) leakage rate acceptance criteria, as outlined in the memorandum from H. Denton to V. Stello on February 14, 1985, has been accepted by CRGR (July 24,1985). This revised acceptance criteria may be adopted for Diablo Canyon Units 1 and 2.
Enclosure (1) contains the revised Standard Technical Specification pages from the February 14, 1985 memorandum. The Diablo Canyon Technical Specifications are to be changed as noted in Paragraph 3.4.6.2 f. and 4.4.6.2.2 e. of the enclosure.
O t
Rob rt J. Bosnak, Acting Assistant Director for Components and Structures Engineering Division of Engineering
Enclosure:
As stated cc:
J. Knight R. Bosnak F. Cherny C. Moon M. Virgilio
- 0. Rothberg G. Edison D. Crutchfield H. Schierling R. Kirkwood H. Brammer CONTACT: Owen Rothberg, MEB, P-522
._49-27864 -
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ENCLOSURE (1)k 10F 2 WESTINGHOUSE PWR STANDARD TECHNICAL SPECIFICATIONS REACTOR COOLANT SYSTEM OPERATIONAL LEAKAGE LIMITING CONDITION FOR OPERATION 3.4.6.2 Reactor Coolant System leakage shall be limited to:
a.
No PRESSURE BOUNDARY LEAKAGE, b.
1 GPM UNIDENTIFIED LEAKAGE, c.
1 GPM total primary-to-secondary leakage through all steam gener-ators not isolated from the Reactor Coolant System and (500) gallons per day through any one steam generator not isolated from the Reactor Coolant System, d.
10 GPM IDENTIFIED LEAKAGE from the Reactor Coolant System, and i
e.
GPM CONTROLLED LEAKAGE at a Reactor Coolant System pressure of Fff5
- 20 psig.
f.
- 0.5 GPM leakage per nominal inch of valve size up to a maximum of l
5 GPM at a Reactor Coolant System pressure of 2235 1 20 psig from any Reactor Coolant System Pressure isolation Valve specified in Table 3.4-1.
APPLICABILITY: MODES 1, 2, 3, and 4.
ACTION:
a.
With any PRESSURE B0UNDARY LEAKAGE, be in at least HOT STANDBY 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 />.
c.
With any Reactor Coolant Syst4m Pressure Isolation Valve leakage 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 or deactivated automatic valves,
- Replaced the phrase "One GPM Leakage."
f
n e,
ENCLOSURE (1)k 2 0F 2 REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS 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 />.
4.4.6.2.1 Reactor Coolant System leakages shall be demonstrated to be within each of the above limits by:
Monitoring the containment atmosphere (gaseous or particulate) a.
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 pocket 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 when the Reactor Coolant System pressure is 2235 1 20 psig at least once per 31 days 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 />.
Monitoring the reactor head flange leakoff system at least once per e.
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, except that in lieu of any leakage testing required by Specification 4.0.5, each valve shall be demonstrated OPERABLE by verifying leakage to be within its limit:
a.
At least once per 18 months.
t b.
Prior to entering MODE 2 whenever the plant has been in COLD SHUTDOWN for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or more and if leakage testing has not been performed in the previous 9 months.
Prior to returning the valve to service following maintenance, c.
repair or replacement work on the valve.
l d.
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.
- e.
As outlined in the ASME Code,Section XI, paragraph IWV-3427 (b).
l The provisions of Specification 4.0.4 a e not applicable for entry into MODE 3 or 4.
"Added.
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L AUG 161985 3HiIPD hIEIPS bOMYIDI bppfahS.OMSM.
FOR THE oISTRICT OF COLUMBI A CIRCULT l
No. 84-1410, et a1.
September Term,19 84 San Luis Obispo Mothers for Peace, et al.,
Petitioners United States Court of Appeals v.
For the District of Columt'.a Circuit United States Nuclear Regulatory Commission and United States of America,
{.
E 121985 Respondents
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Pacific Gas and Electric Company, G E O R G E A. E15 H E R CLEMX Intervenor BEFORE: Robinson, Chief Judge, Wright, Tamm, Wald, Mikva, Edwards, Ginsburg, Bork, Scalia and Starr, Circuit Judges 0RDER It is ORDERED, by the Court, en banc, sua sconte, that petitioners in tne captioned case shall file supplemental briefs on or before September 3, 1935.
Respondent may file a response on or before September 24, 1985.
Petitioners' reply, if any, must be delivered to the Clerk's Office by 4:00 p.m.
l on September 30, 1985.
In addition to any other issues that counsel may wish to cresent, counsel are directed to address the following specific issues:
i (a) The rationality of the Commission's decision not to require emergency planning for earthquakes.
(b) Wh'at degree of consideration should the Court give to the transcripts of the Commission meetings at rehearing.
Briefs shall not exceed 20 printed pages in length (28 pages if reproduced by other than standard typographical means).
Petitioners' reply brief, if any, shall not exceed 10 printed pages (14 pages if reproduced by other means). An original and twenty-nine copies of each brief shall be filed.
In addition, counsel for each of the parties shall file thirty copies of all briefs previously filed. And it is lem J'
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L.
Unifeh @fafes Eaurf of Appeals FOR THE DISTRICT OF COLUMBI A CIRCulT No. 84-1410, et al.
September Term,19 84 2-FURTHER ORDERED, by the Court, en banc, rua sponte, that oral argum.ent in the captioned case shall tale place on October 3,1985, at 1:30 p.m.
Unless otherwise ordered, each side shall be allocated thirty i
r.inutes for the argument of its case.
Per Curiam For The Courtab6l<b George
. Fisher Clerk l
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