ML20100Q386
| ML20100Q386 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 03/01/1996 |
| From: | NORTHERN STATES POWER CO. |
| To: | |
| Shared Package | |
| ML20100Q380 | List: |
| References | |
| NUDOCS 9603110618 | |
| Download: ML20100Q386 (5) | |
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Exhibit B Monticello Nuclear Generating Plant Revision 1 to License Amendment Reauest Dated December 11.1995 Proposed Changes Marked Up on Existing Technical Specification Pages Exhibit B consists of the existing Technical Specification pages with the proposed changes marked up on those pages. Existing pages affected by this change are listed below:
ESAR 171 1
9603110618 960301 PDR ADOCK 05000263 P
3.0 LIMITING CONDITIONS FOR OPERATION 4.0 SURVEILLANCE REQUIREMENTS d.
At least once per week the main steam-line power-operated isolation valves shall be exercised by partial closure and subsequent reopening.
2.
In the event any Primary Containment automatic 2.
Whenever a Primary Containment automatic isolation valve becomes inoperable, reactor isolation valve is inoperable, the position of operation in the run mode may continue at least one fully closed valve in each line provided at least one valve in each line having an inoperable valve shall be recorded having an inoperable valve is closed.
daily.
3.
If Specification 3.7.D.1 and 3.7.D.2 cannot 3.
Deleted be met, initiate normal orderly shutdown and have reactor in the cold shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
4.
The seat seals of the drywell and suppression I
chamber 18-inch purge and vent valves shall be replaced at least once every L,. c. S: x OfcfchS 5 A Type. c ic}ab.fCILS. M Oe.fIoMc.
C-3e -tes.% S e4 m
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O(s+9Cd fCf S tA/ VCIl lad 4 reg (A.i/c.Me.nt Y,7. A, 2, b identiheg a
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dcyaao-hog Oca +he. sed seds of oJ l d ry wcfl u d s,a pp <c s.s.;on c k c e b e.< 18-inck f Wege.
AAd \\/C^k Valves sI ll 3.7/4.7 be,
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REV m
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Exhibit C Monticello Nuclear Generating Plant Revision 1 to License Amendment Reauest Dated December 11.1995 Revised Technical Specification Pages Exhibit C consists of the Technical Specification pages with the proposed changes incoroorated. Existing psges affected by this change are listed below:
P_RER 171
m 3.0 LIMITING CONDITIONS FOR OPERATION 4.0 SURVEILLANCE REQUIREMENTS d.
At leist once per week the main steam-line power-operated isolation valves shall be exercised by partial closure and subsequent reopening.
2.
In the event any Primary Containment automatic
- 2. Whenever a Primary Containment automatic isolation valve becomes inoperable, reactor isolation valve is inoperable, the position operation in the run mode may continue of at least one fully closed valve in each provided at least one valve in each line line having an inoperable valve shall be having an inoperable valve is closed.
recorded daily.
3.
If Specification 3.7.D.1 and 3.7.D.2 cannot
- 3. Deleted be met, initiate normal orderly shutdown and have reactor in the cold shutdown conditions within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
- 4. The seat seals of the drywell and suppression chamber 18-inch purge and vent valves shall be replaced at least once every six operating cycles.
If periodic Type C leakage testing of the valves performed per surveillance requirement 4.7.A.2.b identifies a common mode test failure attributable to seat seal degradation, then the seat seals of all drywell and suppression chamber 18-inch purge and vent I
valves shall be replaced.
1 3.7/4.7 171 REV
f Exhitut D Measured Leakage of Monticello Primary Containment Purge and Vent Valves (leakage in SCFH)'
AO-2377 AO-2378 AO-2381 AO-2383 AO-2386 AO-2387 AO-2896 AO-2379 CV-2384 CV-2385 AO-74250 i
AO-2380 AO-74248 AO-7424A AS AS AS AS AS AS AS AS AS AS AS AS AS AS l
FND' LEFT*
FND*
LEFT*
FND*
LEFT*
FND*
LEFT*
FND*
LEFT*
FND*
LEFT*
FND*
LEFT*
1986 Outage 1.91 0.70*
3.94 3.94*
O 3.18' 7.41 1.81*
3.87 2.40*
1.7 1.32*
3.45 1.72*
i 1987 Outage 0
10.24 6.36 1.81 4.64 4.39 4.83 1989 Outage 0
4.20 3.98 3.24 3.09 2.63 6.25 1991 Outage 2.03 0.51' 3.15 3.94*
2.79 4.78*
1.82 2.72*
4.25 16.63*
4.39 2.20' 3.47 1.39*
1993 Outage 1.02 3.15 7.43 3.33 2.42*
12.87 3.07 4.51 1.74*
1994 Outage 0.27 1.48 1.86*
5.00 2.05 2.71*
8.12 7.90 2.41 0.11*
t Note 1:
Primary Containment Purge and Vent 18-mch valves are idenbfied in bold text. Due to testing configurabons, several of the valves, i
l which are subject of the requested licensing amendment, are tested in conjuncbon with additional valves. Maximum allowed leakage for these test configurations is 17.2 SCFH at a test pressure of 42 psig.
j Note 2-As Found leakage test results.
(
t Note 3:
As Left Leakage test results: after performance of correchve maintenance, preventabve maintenance, or after related activities that could have an adverse impact on leakage performance. Lack of test data indicates no such actmbes occurred for Pnmary Containment Purge and Vent valves dunng this period.
l
!'I Note 4:
As left testing on AO-2377, AO-2378, AO-2381, AO-2383, AO-2386, AO-2387 and AO-2896 follomng T-shaped elastomer seal replacement.
i Note 5:
As left testing due to maintenance on AO-7424A, AO-74248 and AO-74258.
[
i Note 6:
' As l eft testing due to concem for potenbal fouhng of seats due to torus pamtmg actmties.
l
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