ML20032D525
| ML20032D525 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 11/09/1981 |
| From: | DUQUESNE LIGHT CO. |
| To: | |
| Shared Package | |
| ML20032D524 | List: |
| References | |
| NUDOCS 8111170217 | |
| Download: ML20032D525 (8) | |
Text
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Attachment A TABLE 3.3-3 (C:ntinued)
.A..L. N 0.... o.
im t n
- rip functicn may be bypassed in this MCDE belcw ?-11.
T zis
-'The channel (s) asscciated with the protective functions derived frem the cut of service Reacter Ccclant L:cp shall be placed in the tripped mcde.
F CT. n i.e_i n i u.,.--
tu, mo ACTION 13 - With.the nu=ber of 0?EFA5LE Channels cne less than the Tc:ai Number of Channels, be in HOT STA.C5Y wi-hin 5 hcurs and in
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COLD SH'JTOGWN wi:nin -he f611: wing 30 hcurs; hcwever, ene channel may be by assed for u: :: 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveinance
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ACTION la. With the number cf CFEFAELE Channels One less than the Total Nu=::er of Channeis:
- a. Eel:w F-il er F-12, P ace the in:;erable channei in the i
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' Channel !* CFE?f 5LE Sta*us Within 21 hcurs after exceecin:
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rest:re - e inc: era.ie :nannei
- 0?E.:J5LE status within 2 h urs er be in HOT SHUT CWN wi:nin :te felicwing 12 hcurs; hewever, one channel ass:ciatad with an 0;erating lecp -.ay be bypassed for up :: 2 hcurs f:r surveillance testing per 5:ecification 4.3.2.1.1.
ACTION 15 - With :.te number cf CFE?A5LE Channels one less than the
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- a. 5eicw ?.11 cr ?-12, place :.e in:;erable channel in the by: ass c:ndi icn; rest:re the inc; 2rabie channei to 0?IFAELE status wi nin 20 h urs after exceeding ?-11 er F-12; otherwise be in at lets: HOT SHUTUCWN within the
- ,:icwing 1. hcurs.
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%d PROPOSED 'a'ORDING 8211170217 81110M PDR ADOCK 05000334 P
i 4.0tr.ch:: t S CONTAINMENT SYSTEMS CONTAINMENT LEAKAGE LIMITING CONDITION FOR OPERATION-3.6.1.2 Containment leakage rates shall be limited to:
a.
An overall integrated leakage rate of:
74 $c,urs.10 percent by weight of the containment air per
<L 0
1.
at P, (38.3 psig), or a
b.
A ccmbined leakage rate of < 0.60 L, for all penetrations and valves subject to Type 3 and C tests as identified in Table 3.51, when pressurized to P '
a APPLICABILITY: MODES 1, 2, 3 and 4 ACTION:
With either (a) the measured overall integrated containment leakage rate-exceeding 0.75 L, or (b) with the measured ccmbined leakage rate for a
all penetrations and valves subject to Types 3 and C tests exceeding restore the leakage rate (s) to within the limit (s) crior to 0.60 L,ing the Reactor Coolant System temcerature above-200*F ------
increas
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SURVEILLANCE REQUIREMENTS 4.5.1.2 The centaircent leakage rates shall be demonstrated at the following test schedule and shall be determined in ccnformance with the criteria specified in Appendix J of 10 CFR 50 using the metheds and provisiens of ANSI N 56.8-1981:
l Three Type A tests (Overall Integrated Containment Leakage a.
Rate) shall be conducted at 40 + 10 month intervals during shutdown at P, (38.3 psig) during each 10-year service pericd.
The third test of each set shall be conducted during the shutdewn for the 10-year plant inservice inspection.
EEAVER VALLEY - UNIT 1 3/2 5-2 PROPOSED WORDING
~I i
Attachment B 1
CONTAINMENT SYSTEMS SURVEILLANCE REOUIREMENTS (Continued)
If any periodic Type A test fails to meet.75 L, the b.
test schedule for subsequent Type A tests shall,be reviewed and approved by the Ccanission.
If two consecutive Type A
, a Type A test shall be performed at tests fail to meet.75 L,il two ecnsecutive Type A tests meet least every 18 months unt
.75 L, at which time the above test schedule may be resumed.
The accuracy of each Type A test shall be verified by a c.
supplemental test which:
1.
Confirms the accuracy of the Type A test by verifying that the difference between succlemental and Tyce A est data is within 0.25 L
- a 2.
Has a duration sufficient to accurately establish the change in leakage for between the Type A test and the supplemental test.
3.
Requires the quantity of gas injected into the etntain-ment or bled frcm the centairment during the supplemental test to be equivalent to at least 25 percent of the total
~
~~
~~ measured leakage rate ~at-Pa (3Sv3-psig).-
d.
Tyce B and C tests shall be conducted with gas at 4 (38.3 asig) or as specified by ANSI N56.8-19.81 at intervals no greater than 24 months _except for tests involving:
1.
Air locks.
2.
penetrations using ccntinucus leakage monitoring systems, and 3.
Valves pressuri:ed with fluid frcm a seal system.
Air lecks shall be tested and demonstrated OPERABLE per Sur-e.
veillance Requirement 4.5.1.3.
f.
Leakage frcm isolation valves that are sealed with fluid frcm a seal system may be excluded, subject to the previsions of Appendix J,Section III.C.3, when determining the ccabined leak-age rate provided the seal system and valves are pressurized to at least 1.1C P (42.1 psig) and the seal system cacacity is adequatetomaifitainsystempressureforatleast30 days.
SEAVER VALLEY - UNIT 1 3/4 6-3 PROPOSED WORDING
_ _ _. - ~.
Attachment C.
TABl.E 3.6-1 (Contined)
ISOLATION TIME os val.VE NUMBER TESTABLE DURING (88#)
h
.INSIDE/OUTSIDE FUNCTION PLANT OPERATION INSIDE/0UTSIDE 1
trl C. Containment Purge and Exhaust l
$e 1.
VS-D-5-3B VS-D-5-3A Containment Purge Exhaust No 8(1) 8(1)
N 2.
VS-D-5-5B VS-D-5-5A Containment Purge Sypply No 11(1) 8(1) i 3.
VS-D-5-6 Containment Purge Vacuum Breaker No N/A N/A l'
0 U
D. Manual i
i 1.
1C11-181 MOV-Cll308A Seal Injection Water to RC Pump No N/A N/A 2.
1C11-182 MOV-CII30815
. Seal Injection Water to RC Pump No N/A N/A i
3.
1C11-183 MOV-Cll308C Seal Injection Water.to RC Pump No N/A N/A y
j g
- 4.
MOV-Cil142 Reactor Coolant System Letdown Yes N/A N/A l
g g
- 6 MOV-CC112A3 1CCR-251 CC*l from RilR lix & RilR Pump Seal Coolers Yes N/A N/A E
i
h
- 9 MOV-FW-151A Auxiliary Feedwater Yes N/A N/A c
- 10 MOV-FW-151B Auxiliary Feedwater Yes N/A N/A 6
- 11 MOV-IN-LSIC Auxiliary Feedwater Yes N/A N/A
- 12 MOV-IN-151D Auxiliary Feedwater Yes N/A N/A
- 13 MOV-FW-151E Auxiliary Feedwater Yes N/A N/A
- 14 MOV-IN-151F Auxiliary {Feedwater Yes N/A N/A
- 15 MOV-RW_04A Riverwater to Recire. Spray lix Yes N/A N/A
- 16 MOV-RW104C RiverwateftoRecire.Spraylix Yes N/A N/A
- 17 MOV-RW104B Riverwater to Recire. Spray lix Yes N/A N/A
- 18 MOV-RW104D Riverwated to Recire. Spray lix Yes N/A N/A t
(1) Applicable in mode 6 only.
The provisions of specification 3.0.4 are not applicable. The Containment Purge Exhaust and Supply valves will be locked shut during operation in modes 1, 2, 3, and 4.
i
Attachmsnt C REFUELING OPERATIONS CONTAINMENT BUILDING PENETRATIONS LIMITING CONDITION FOR OPERATION 3.9.4 The containment building penetrations shall be in the following status:
a.
The equipment door closed and held in place by a minimum of four bolts, b.
A minimum of one door in each airlock is closed, and c.
Each penetration providing direct access from the containment atmosphere to the outside atmosphere shall be either:
1.
Closed by an isolation valve, blind flange, or manual valve, or 2.
Exhausting at less than or equal to 7500 cfm through OPERABLE Containment Purge and Exhaust Isolation Valves with isolation times as specified in Table 3.6-1 to l
OPERABLE HEPA filters and charcoal absorbers of the Supplemental Leak Collection and Release System (SLCRS).
APPLICABILITY: During CORE ALTERATIONS or move =ent.of irradiated fuel
.. within__ the_ containment..
ACTION:
With the requirements of the above specification not satisfied, ic=ediately:
suspend all operations involving CORE ALTERATIONS or movement of irradiated fuel in the containment. The provisions of Specification 3.0.3 are not applicable.
SURVEILLANCE REOUIREMENTS 4.9.4.1 Each of the above required containment penetrations shall be determined to be in its above required condition within 150 hours0.00174 days <br />0.0417 hours <br />2.480159e-4 weeks <br />5.7075e-5 months <br /> prior to the start of and at least once per 7 days during CORE ALTERATIONS or movement of irradiated fuel in the containment.
4.9.4.2 The containment purge and exhaust system shall be demonstrated OPERABLE by:
a.
Verifying the ficw rate through the SLCRS at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the system is in operation.
b.
Testing the Containment Purge and Exhaust Isolation Valves per the applicable portions of Specification 4.6.3.1.2, and c.
Testing the SLCRS per Specification 4.7.8.1.
BEAVER VALLEY - UNIT 1 3/4 9-4 PROPOSED WORDING
m acamanr.c REFUELING OPERATIONS CONTAINMENT PURGE AND EXHAUST ISOLATION SYSTEM LIMITING CONDITION FOR OPERATION 3.9.9 The Containment Purge and Exhaust isolation system shall be OPERABLE.
APPLICABILITY: MODES 5 and 6*
ACTION:
With the Containment Purge and Exhaust isolation system inoperable, close each of the purge and exhaust penetrations providing direct access from the containment atmosphere to the outside atmosphere.
The pro-visions of Specification 3.0.3 are not applicable.
- NOTE:
The dampers must meet the isolation requirements of Table 3.6-1 l
for Mode 6 only.
SURVEILLANCE REQUIRE m"IS 4.9.9 The Containment Purge and Exhaust isolation system shall be demonstrated OPERABLE within 150 hours0.00174 days <br />0.0417 hours <br />2.480159e-4 weeks <br />5.7075e-5 months <br /> prior to the start of and at least once per 7 days during CORE ALTERATIONS by verifying that contain-ment Purge and Exhaust isolation occurs on manual initiation and on a high-high radiation signal from each of the containment radiation monitoring instrumentation channels.
l BEAVER VALLEY - UNIT 1 3/4 9-9 PROPOSED WORDING
Attachmint D REACTOR COOLANT SYSTEM w
STEAM GENERATORS LIMITING CONDITION FOR OPERATION 3.4.5 Each steam generator shall be OPERABLE.
APPLICABILITY: MODES 1, 2,
3, and 4.
ACTION:
With one or more steam generators inoper:ble, restore the inoperable generator (s) to OPERABLE status prior to increasing T,y above 200*F.
SURVEILLANCE REQUIREMENTS 4.4.5.1 Steam Generator Sample Selection and Inspection - Each steam generator shall be determined OPERABLE during shutdown by selec' ting and inspecting at least the minimum number of steam generators specified in Table 4.4-1.
4.4.5.2 Steam Generator Tube Sample Selection and Inspection -
The steam generator tube minimum sample size, inspection result classification, and the corresponding action required shall be as specified in Table 4.4-2.
The inservice inspection of steam generator tubes shall Le performed at the frequencies specified in Speci-fication 4.4.5.3 and the inspected tubes shall be verified acceptable-per the acceptance c ri t e ria o f-Spe cifica tion -4. 475 r4v- -
Steam generator tubes shall be examined in accordance with the method prescribed in Article 8- " Eddy Current Examination of Tubular Products, as contained in ASME Boiler and Pressure Vessel Code, Section V-
"Non-destructive Examination," and referenced in ASME Boiler and Pressure Vessel Code - Appendix IV to Section XI as amended in the Summer 1976 Addenda " Inservice Inspection of Nuclear Power Plant Components."
The tubes selected for each inservice inspection shall include at least 3% of the total number of tubes in all steam generators; the tubes selected for these inspections shall be selected on a random basis except:
a.
Where experience in similar plants with similar water chemistry indicates critical areas to be inspected, then at least 50% of the tubes inspected shall be from these critical a reas.
b.
The first inservice inspection (subsequent to the preservice inspection) of each steam generator shall include:
1.
All nonplugged tubes that previously had detectable wall penetrations (greater than 20%), and 2.
Tubes in those areas where expe,rience has indicated potential problems.
BEAVER V ALL EY-U NIT 1 3/4 4-8 PROPOSED WORDING
a Attachm:nt E REACTCR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued) a.
At the first refueling outage, dye penetrant inspections shall be performed on all six reactor vessel nozzles and volumetric inspections shall be performed on at least two nozzles in the same manner as that conducted in the baseline inspection.
b.
At the second refueling outage, a dye penetrant examination shall be performed on all six nozzle to safe end welds and an ultrasonic examination shall bc_ performed on all six nozzle to safe end welds from the outside diameter.
At the third refueling outage, a dye penetrant examination shall be performed or all six nozzle to safe end welds and an-ultra-sonic examination shall be performed on all six nozzle to scfe end welds from the outside diameter. Ultrasonic examination shall be performed on the threa outlet nozzle to safe end welds from the inside diameter, c.
Defects found during these inspections shall be evaluated to determine their significance and reported to the Commission pursuant to Technical Specification 6.9.1.8.c.
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i..s BEAVER V ALLEY-U NIT 1 3/4 4-29 l
PROPOSED WORDING l
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