ML20214K994
| ML20214K994 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 11/24/1986 |
| From: | Andrews R OMAHA PUBLIC POWER DISTRICT |
| To: | Thadani A Office of Nuclear Reactor Regulation |
| References | |
| LIC-86-616, TAC-62069, NUDOCS 8612020538 | |
| Download: ML20214K994 (3) | |
Text
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Omaha Public Power District 1623 Harney Omaha, Nebraska 68102 2247 402/536-4000 November 24, 1986 LIC-86-616 Mr. Ashok C. Thadani, Project Director PWR Project Directorate #8 Division of PWR Licensing-B Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555 l
References:
1.
Docket No. 50-285 2.
Application for Amendment of Operating License dated August 5, 1986
Subject:
Instrumentation for the Detection of Inadequate Core Cooling -
Technical Specifications
Dear Mr. Thadani:
The Technical Specifications for instrumentation for the detection of inade-quate core cooling were filed with the NRC in Reference 2.
Since that time, the Omaha Public Power District has had conversations with the staff's tech-nical reviewer concerning this matter. Accordingl.", Table 2-10 of our previous submittal has been replaced with the attached. We believe this change will be responsive to the reviewer's concerns. OPPD wishes to have 60 days from the date the revised Technical Specifications are issued in order to implement the new specs.
If you have any additicnal questions, please do not hesitate to contact us.
Sincerely, R. L. Andrews Division !!anager Nuclear Production RLA/me cc: LeBoeuf, Lamb, Leiby & MacRae 1333 New Hampshire Ave., N.W.
Washington, DC 20036 0
h0 D. E. Sells, NRC Project Manager i\\g P. H. Harrell, NRC Senior Resident Inspector
\\
8612O20538 861124 PDR ADOCK 05000295 p
PDR ai oppentumeu
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ATTACHMENT DETAILS AND JUSTIFICATION for changes to Table 2-10 as previously submitted in Application for Amendment of Operating License dated August 5,1986.
Due to an NRC staff concern regarding the proposed ICCI Technical Specifications Limiting Conditions for Operations, a conference call was held with the staff reviewer. The concerns were two-fold.
First was that the time limits in the LC0's for the Subcooled Margin Monitor and Core Exit Thermocouples were more lenient than the Standard Technical Specifications and NRC guidance. This made the specification, as proposed, unacceptable.
To resolve this concern, two additional footnotes, consistent with Standard Technical Specification LC0 time limits, have been added.
The second concern involved an inconsistency between the format of Standard Tech. Specs. and OPPD's Tech. Specs.
The basis of the concern is that OPPD's Tech. Specs. do not contain a " Required Number of Channels" specification.
The NRC first recommended that we add a column entitled " Required Number of Channels" and provide the appropriate numbers.
OPPD.has added a " Required Number of Channels" column to Table 2-10.
In order to maintain consistency throughout the table, the appropriate numbers have been added for all instruments.
We believe that this revised specifi-cation should serve to resolve the NRC's concerns, and should be granted.
I
.b
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TABLE 2-10 Post-Accident Monitoring Instrumentation Operating Limits dquired Minimum
,,m fU) plo,de.g Ope W e Instrument Chancsh._
Channels Action 1.
Containment Wide Range Radiation Monitors (RM-091A & B) d 2
(a) 2.
Wide Range Noble Gas Stack Monicor RM-063L (Noble Cas Portion Only)
- I 1
(a)
RM-063M (Noble Gas Portion Only)
/
1 (a)
RM-063H (Noble Gas Portion Only)
/
1 (a) it 3.
Main Steam Line Radiation Monitor (RM-064) f 1
(a) 4.
Containment Hydrogen Monitor (VA-81A & B) 4
'1 1 (b)(c) 5.
Containment Water Level Narrow Range (LT-599 & LT-600)
/
1 (d)
Wide Range (LT-387 & LT-388) 4 1/
(b)(c) 6.
Containment Wide Range Pressure cl.
%I (b)(c) 7.
Reae+o r C..ia.nt Susk m 5"!cd margin 1%n dor-a i
.ch)ti)
- 8. Cove w TW'"oc=P cs &E'T*)
&r.mt
'hnt WN i
t
- 9. R oc/., ve,.e/ wt( w7c) ge)
/ '")
M/)
9 (a) With the number of OPERABLE channels less than required by the minimum Lchannelsf operable / requirements, initiate' the pre-planned alternate method of monitoring the appropriate parameter (s) within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, and 1.
either restore the inoperable channel (s) to.0PERABLE status within 7 days of the event, or i
2.
prepare and submit a special report to the Commission pursuant to specification 5.9.3 within 14 days following the event outlining the action taken, the cause of the inoperability, and the plans and schedules for restoring the system to SPERABLE status, ""g g a m,,vlz.< et cP& M a s c w m h Les -n m & & e mn'A 0""*
t<
n (b) With ene-d :::: Tin p:rdle, restore the inoperable menteer to OPERABLE status within 30 days or be in at least HOT SHUTDOWN within he next k"
"I
- cy, &c tk Min %m etardici (c) With beeWchannels ine(p: dic, t) n, s a
restore at least one cWnnel t'o 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 SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
M (d) With the number of OPERABLE channels less than required by the minimum Lehannels / operable f requirements, operation may continue until the next cold shutdown, at which time the required channel (s) shall be made v
AmendmentNo.$Z,53',S3,f 2-98
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