ML20095J434
| ML20095J434 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 12/20/1995 |
| From: | NORTHERN STATES POWER CO. |
| To: | |
| Shared Package | |
| ML20095J418 | List: |
| References | |
| NUDOCS 9512270098 | |
| Download: ML20095J434 (4) | |
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Exhibit B
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Monticello Nuclear Generating Plant License Amendment Reauest dated December 20.1995 (Suppliment to August 15, and November 14 submittals) 4 Proposed Changes Marked Up on Existing i
Technical Specification Pages Exhibit B consists of the existing Technical Specification page with the proposed changes marked up on the page. The existing page affected by this change is listed below-1 j
M 159 i
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9512270098 951220 PDR ADOCK 05000263
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, P,DR,
Perform required visual cxaminations and leakage rate testing forType A V,C Ombel mAU f^u r^ g0" fA gg,3e contrinment integrated leakage rata tests in accordance with 10 CFR $0 s
Appendix J Option B as modified by approved exemptions, and ReQuiarary,
of.
v-Guide 1.163 dated September 1995. Perform Type B and C tests in accordanop
-. with 10 CFR 50 Appendix J Option A as modified by approved exemphon 4
3.0 LIMITING CONDITIONS FOR OPERATION 4.0 SURVEILLANCE REQUIREM I -
=
s r
b.
When Primary Containment Integrity is required, b
Tl pr ma cont nm age ryes
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l ue. id leakage rates shall be limited to:
tall b demon rated -
th; fs' a i.,
a u.or -
(d te st-edul nd rhdb: d:
sinc?
for ri b.: cri ria, m ods I
1.
An overall integrated leakage rate of less provi[:r.::onsof[d
.- r 50; eenM
~T a.
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I than or equal to La, 1.2 percent by weight an 0 CFR P t ochfAai 3y ofprove e.f.e rw rion of the containment air _per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at Pa, e
42 psig.
g y 4g g g k
f3 l en g--
J q
j --
l.
Tl ee Type A overall integrate 2.
A combined eakage rate of less than or equal cont.
ent leakage rate t shall to 0.6La for all penetrations and valves, be conduc at 40110 h intervals
- crp-fer nir eten- ::c'" ter E cc, during shutdo at _ a during each subject to Type B and C tests when pressurized 10-year servi p
od.
The third tl2.psig.
test of e set shal conducted to Pa 3
4L duri te shutdown for tt 0-year 3.
Less than or equal to l'.5 scf per hour or all t inservice inspection.
eny ^=e main steam isolation valveSwhen tested D ele t-d at 25 ps' 2.
any periodic Type A test falls meet 75La, the test schedul or With the measured over integrated primary subseque T pe A tests sh be containment leakage te exceeding 0.75La, or the reviewed and roved the Commission.
measured combined 1 kage rate for all penetrations If two consecuti e A tests fall to and valves,
- a a +-
an e"-
ie^' -+'^-"a--
meet 0.75La, a eA t shall be TypeB[ndCtestingexceed
. La, or I
performed a east every onths until I N the measgred leak rate exceeding 11.5 f2 per hour two con utive Type A tests m 0.75La, for caf r main steam isolation valves restore at w ci time the above test sche le leakage rates to less than or equal to these values be resurped.
prior to increasing reactor coolant system temper-D e.\\ e_Te, d ature above 212
- F o r, alternatively, restore 3.
e A test leakage rates s measured leakage rates to within these limits within calculate observ a converted one hour or be in at least tiot Shutdown within the to absolute va analyses 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 within the shall ormed to select ced following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
integrated leakage measuremen.
stem.
iT ie rest of the seco ar ine} m3$ ywum hDQ yod m.
I service perio<
onducted during i
~ 3n._LM9 e ueling outage.
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3.7/4.7 159
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d Exhibit C l
Monticello Nuclear Generating Plant 4
License Amendment Reauest dated December 20.1995 (Suppilment to August 15, and November 14 submittals)
Revised Technical Specification Page Exhibit C consists of the Technical Specification page with the proposed changes incorporated. The existing page affected by this change is listed below.
U 159 1
L 12/2006 NsP ROATALARWPPJS2. DOC
1
(
3.0 LIMITING CONDITIONS FOR OPERATION 4.0 SURVEILIANCE REQUIREMENTS i
b.
When Primary Containment Integrity is required, b.
Perform required visual examinations and leakage rates shall be limited to:
leakage rate testing for Type A containment integrated leakage rate tests in accordance 1.
An overall integrated leakage rate of less with 10 CFR 50, Appendix J, Option B, as than or equal to La, 1.2 percent by weight modified by approved exemptions, and Regulatory of the containment air per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at Pa, Guide 1.163 dated September 1995. Perform Type l
42 psig.
B and C tests in accordance with 10 CFR 50, I
Appendix J, Option A, as modified by approved 2.
A combined maximum flow path leakage rate exemptions.
of less than or equal to 0.6La for all penetrations and valves, subject to Type B 1.
Deleted l
and C tests when pressurized to Pa, 42 psig.
2.
Deleted 3.
Less than or equal to 46 scf per hour 3.
Deleted combined maximum flow path leakage for all main steam isolation valves when tested at 4.
Deleted 25 psig.
5.
Deleted With the measured overall integrated primary containment leakage rate exceeding 0.75La, or the measured combined leakage rate for all penetrations and.alves subject to Type B and C testing exceeding 0.6La, or the measured combined maximum flow path leakage rate exceeding 46 scf per hour for all main steam isolation valves, restore leakage rates to less than or equal to these values prior to increasing reactor coolant system temperature above 212*F or, alternatively, restore measure leakage rates to within these limits within one hour 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 /> and in Cold Shutdown within the I
following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
159 3.7/4.7
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