B12724, Revised Inservice Insp Testing Program. W/12 Oversize Drawings
| ML20236H926 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 10/31/1987 |
| From: | NORTHEAST NUCLEAR ENERGY CO. |
| To: | |
| Shared Package | |
| ML20236H912 | List: |
| References | |
| B12724, PROC-871031, NUDOCS 8711050025 | |
| Download: ML20236H926 (117) | |
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Docket No. 50-336
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ATTACHMENT 1 Revised ISI Testing Program i
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4 PUMP OPERATIONAL READINESb l
i TESTING PROGRAM 4
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Pump In-Service Testing 1.
Scope 1
This program describes the procedures for in-service testing of 26 pumps to meet the requirements of Section XI of the ASME Code, Subsection IWP, "In-Service Testing in Nuclear Power Plants."
1 In-service testing is required for all Class 1, 2, and 3 pumps (both centrifugal and displacement types) that are provided with an i
emergency power source.
Except that pumps which are supplied with j
emergency power solely for operating convenience are excluded, j
Drivers are excluded except when the pump and driver form an integral unit and the pump bearings are in the driver.
All tests and examination procedures required by Subsection IWP including schedules, reference values, the location and type of measurement for each of the required test quantities, records of the results, and all correctfve action taken shall be defined and performed by NSECO for Millstone Unit No. 2.
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2.
Test Procedure i
In-service tests of electric motor-driven pumps shall be conducted f
l with the pump operating at nominal motor speed.
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I lA series of reference values are determined for-quantities listed' below, as observed or measured when the equipment is known.to be operat:ing correctly.
1 In-Setvice Test Qu'antities 5
Inlet Pressure, Pi e-Differential Pressure, P
l Flow Rate, Q Vibration, V Proper Lubricant Level or Pressure Speed (Variabic Speed Pumps Only)
In pince of V (Vibration Amplitude), NNECO will use a Vibration i
Signature Analysis' Program as described in Section 5 and Relief Request RR-TkT-1.
This program also eliminates the requirement for.
moasuring bearing temperatures annually due to the program's ability to detect bearing problems at a very early stage.
For additional information, see Relief Request RR-IkT-2.
In an in-service test, these quantities are remeasured and compared with the reference values to determine if corrective action is needed.
k' hen a reference value or set of values eay have been -
affected by replacement, repair or routine servicing of the pump, a new reference value er set of values shall be determined or the i.
previous value reconfirmed by an in-service test run within 4 days after return of the pump to normal service.
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3.
Test Frequency Each in-service test shall include the nessurement and observation of applicable test quantities.
An in-service test shall be run on each pump, at a frequency and scope as stated in Table IWP.
If possibic, this test frequency shall be maintained during plant shutdown. If the pump is not tested during plant shutdown, it shall be tested within one week after the plant is returned to steady state operation.
Pumps that are operating need not be run or stopped for a special test, provided the plant log shows each such pump was operated at reference conditions and the quantities specified were measured, observed, recorded, and analyzed.
4.
Analysis and Corrective Action All test data shall be analyzed within 4 days after completion of a test. The test quantities are compared with the allowable range of quantities listed in Table IWP-3100-2 of Subsection IWP.
If the specified ranges do not assure the pump will fulfill its function, reduced range limits allowing the pump to fulfill its function may be used in lieu of those in Table IWP-3100-2. These reduced range limits shall be specified in NNECO in the pump testing procedures.
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M The'correctiv'c; action to,be taken by NNECO if the periodically e
acquired' operational data fall's into the calculated! Alert Range or 1
6Required' Action Range.shall be specified in NNECO procedures and
- shall be_ consistent'with Code' Requirements.
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The~ following information~ shal'1 be maintained'by Millst'onc to meet-the requirements for in-service testin'g:
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A' record for.each pump including the name of the manuf acturer,'
1 the model, and the serial number or other identification
.h number.
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An in-service test plan including:
(a) the hydraulic circuit to be used.
I (b) the location and type of measurement for each required test quantity,-
I (c). the test quantity reference values, the limits of Pg (Table IWP-3100-2) and any other required information..
Test record giving portinent information such as test date, l
instruments used, results, corrective action required, and l
signatures of persons conducting and analyzing the test.
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' A record of corrective action and subsequent in-service test
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e f-verifying operational adequacy. - All in-service. test plans and records shall be maintained in accordance with NNECO procedures for control-of QA records.
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5.
Vibration Monitoring Program in lieu of measuring overall vibration amplitude (mils), the j
following vibration monitoring program will be implemented:
(see.
. Relief Request RR-IVP-1).
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Vibration will be monitored at least quarterly using equipment which collects vibration velocity signatures.
Overall, vibration velocity I
(in/sec peak) will be compared to the following acceptance criteria.
Acceptance Range - 0 to 2.5 times Reference Velocity i
Alert Range - 2 2.5 to 5 times Reference Velocity but not greater than 0.325 in/sec (peak) (0.65 in/see for Service Water Pumps) i l
Required Action Range - ? 5 times Reference Velocity but not j
greater than 0.7 in/sec (peak) (1.4 in/see for Service Water Pumps)
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' levels, vibration signatures will be reviewed at least. quarterly to-l j
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-i PUMP (WP) RELIEF REQUEST i
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i Millstone Nuclear Power Station Unit No. 2 Second Ten-Year Interval Relief from In-Service Testing Requirements
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Ralief Request:
RR-IWP-1 Pump Vibration Monitoring In-Service Test l
l Pump Identification:
7 ASME Code Class 2 and 3 Category:
IWP Applicable Pumps:
All pumps as shown on Table IWP
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Pump Function:
Centrifugal and positive displacement pumps that are required to perform a specific function in shutting down the reactor or in mitigating the consequences of an accident.
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- Tablei1WP-3100-l'and IWP-3100'-2, of the-1980 Edition,. Winter.1981 Addenda-requires tha't vibration amplitude be measured.- Paragraph IWP-4510,.
requires that at least one displacement vibration amplitude (peak to' peak-
~l composite) shall=be read during the in-service test, a.
Code Relief Requested:
Relief. is requested f rom measuring the overall vibration amplitude 11.
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1 Basis for Relief:
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Experience has shown that measurement of overall vibration amplitude in~
-l ils does not provide the desired early warning of pump degradation.
.m Vibration amplitude is adequate for measuring unbalance, misalignment, and other' low' frequency failure modes.. It does not give early warning of j
bearing degradation since the magnitude of higher frequency vibration created by such degradation is 10 to 1,000 times lower than the normal
.. pump movements.
Experience at Northeast Utilities has shown that monitoring pump vibration velocity (in/sec) provides earlier warning of
- pump degradation.
Collection and review of vibration "aignatures" (plots of-vibration velocity vs. frequency) over a range from slightly below 1
running frequency to several times running frequency provides optimal
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early warning of pump degradation.
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I Absolute maximum limits are set for t ch pump. 111gher maximum limits are appropriate for the Service Water Pumps since the measurements taken at the upper not.or bearing housing are significantly af fected by the height of the monitoring point above the actual pump, the lack of stiffness in the pump structure, and the fact that the pump natural resonance frequency is.within 5 percent of the running frequency. Millstone Unit 2 experience has shown that the pump vibration levels are extremely sensi-tive to small amounts of unbalance or pump shaft bearing looseness.
Inspections have shown minimal pump or motor degradation after extended operation at vibration levels near the proposed maximum allowable levels.
Because of these factorr, a " service factor" of 2 has been assigned to the vibration limits for these pumps and the maximum allowable vibration adjusted accordingly.
i Preposed Alternative Testing:
For centrifugal pumps, at least two measurements will be taken in a plane perpendicular te the rotating shaft in two orthogonal directions and one measurement ta).en in the axial direction.
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I For reciproct. ting pumps, similar measurements will be taken on a bearing
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housing of '.he crankshaf t.
On vertical line shaft pumps, measurements will be taken on the upper 1
motor bearing housing in three orthogonal directions including one axial 1
direction.
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RR-lWP-1.3 l
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x Vibration will be monitored using equipment which collects vibration sig-natures'over a range from less than one-half running speed to at least-eight times running speed.
1 Overall vibration velocity will be compared to the following acceptance criteria ~for all but the Service Water Pumps:
Acceptable Range - less than 2.5 times reference velocity Alert Range - 2.5 to 5 times reference velocity but not greater than 0.325 in/sec (peak)
.l Required' Action Range - greater than 5 times reference velocity but not greater.than 0.70.in/sec (peak)
Reference velocity shall be the' average overall velocity determined
..during an in-service test at reference conditions when the pump is known to be operating acceptably.
The Service Water Pump maximum values shall be:
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Alert Range - >0.65 in/sec (peak) i Required Action Range - >1.4 in/sec (peak)
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I In addition to the above quantitative analysis of overall vibration levels,' vibration signatures will be reviewed at least quarterly to identify potential bearing degradation or other developing faults. When potential faults are identified, action as required for a pump in the Alert Range of vibration will be initiated.
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l Millstone Nuclear Power Station Unit No.-2 l
Second Ten-Year Interval Relief from In-Service Testing Requirements Relief Request:' RR-IWP-2 IWP, Pump Bearing Temperature (Measuring) Relief.
Component Identification:
'l ASME Code Class:
1,2,63 Category:
IWP Pump Function:
l All safety-related pumps that are required to perform a specific function l
in shutting down a reactor or in mitigating the consequences of an acci-dent and are provided with an emergency power source.
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Code Requirement:
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Table IWP-3100-1 and subparagraph IWP-4310, in the applicable edition of the 1980 ASME Code, including the 1981 Winter addenda requires:
Measuring annually the temperature of centrifugal pump bearings and main shaft bearings of reciprocating pumps at points selected to be responsive to changes in temperature of the bearing.
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g Code Reljgf Requested:
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- Relief is requested;from performing the required bearing' temperature.
measurement int all 26 pumps listed in H111 stone-Unit 2's IWP. pump table.
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f Basis ' f or Relief:
.n Bearing meta 1' temperature monitoring can be effective in' detecting bearing problems. However, the vibration monitoring program established for'M111 stone Unit 2 is significantly more. effective in identifying bearing degradation ~than an annual measurement of bearing temperature.
Bearing' degradation can be detected at a very early stage by vibration signature. analysis. All safety-related pumps are monitored using equip-q ment which is' sensitive to' low' amplitude vibration changes. generated by
.l bearing distress. These' low amplitude' signals are typically.less than one percent of the overall vibration amplitude and cannot.be detected by a simple amplitude _ program conforming to IWP~ minimum requirements.
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However, these changes are routinely detected in the established l
Millstone Unit 2 vibration monitoring program.
In addition, many of the safety-related pumps are constructed such that bearing metal temperature changes will be quickly dissipated throughout the relatively massive housings, oil reservoirs, and attached casings.
As a result., locations at which bearing temperatures could be monitored s
RR-IWP-2.2 l
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I will respond much less than actual' hearing metal temperature, greatly reducing the sensitivity of this method of identifying bearing distress.
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I Turther, bearing temperature changes are f requently very sudden, rise 1
quickly until the bearing wipes, then return quickly to normal or.below i
1 normal as the bearing oil flow increases in the wiped bearing.
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proposed Alternate Testing Record and analyze pump vibration r.ignature at least quarterly.
Signa-ture will be measured as a velocity spectrum.
Signatures will be com-l pared to reference signatures taken when the pump is known to be oper-ating properly.
When comparisons show symptoms of bearing degradation, action as required for a pump in the alert range of Table IWP-3100-2 will be initiated.
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l VALVE OPERATIONAL READINESS TESTING PROGRAM
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COMMENTS TO IN-SERVICE TESTING PROGRAM FOR IWV - VALVES The attached program tables include all valves in the Millstone Unit 2 plant which are required to be identified under Subsection IW of ASME Section XI, 1980 Edition up to and including the Winter 1981 Addenda.
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l The IWV tables listed herein specify the testing frequency and parameters measured or observed for each valve included in the program. When it is not possible or practical to perform a specified in-service test, a
testing alternative is referenced as a relief request.
When relief requesta identify valves will be tested at Cold Shutdown, the following guidelines will apply:
Testing vill commence within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of achieving cold shutdown condi-tions, proceed in an orderly manner (not to interfere with restoring the plant to operation) until complete.
If not completed in a single cold i
shutdown, testing will continue on subsequent cold shutdowns without repeating a specific valve test until the entire list is completed.
I Valves which can be only be tested during cold shutdowns or refueling i
outages shall be retested to verify compliance with the acceptance t
criteria of Relief Request RR-IWV-36 or repaired before plant startup.
Evaluation of acceptable degraded performance or increased frequency
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cause of the originally identified degradation shall be documented in the l
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record of the test.
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SAFETY-RELATED INSTRUMENT AIR ACCUMULATORS.
Valve (s) Served Function Test o
2-AC-15 Containment.? urge Isolation'-
LT I i 3
2-AC-20
..-Containment ?prge IsolWtion LT r
c.
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1 2-51-659 Safety (Injection Minimm flow, LT
' Recirculation Isolation n
s 1
2-SI-660 Saf ety Injection Minimum fles '
LT f
Recirculation Isolation
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2-CH-517 Auxiliary Spray isolation
- ).T 2-CH-518 f
Loop Charging Isolatione Ib' I
L 2-CH-519 Loop Charging Isolation LT l
' R' fueling Water Storage Tani
> LT 2-CH-192 e
7 4
Supply to Charging Pumps i
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N NOTE 1:
This leak test will be performed on the air' supply check valve C.),
to the accumulator each refueling. The test shall verify that N
the accumulator will retain suf ficient > pir to provide opera-m
- )
tion of the valve for 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> after loss of instrument air, instead of method specified in IWV-3424.
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l LEGEND FOR VALVE TESTING TABLES i
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LEGEND FOR VALVE TESTING Exercise' valve full stroke (to theLposition required'to
-Q fulfill'its safety-related function) for. operability every three (3) months.. If applicable, take~ stroke time.
measurements and compare to the stroke time limiting value per Section XI, Article IWV-3410 (see' Note 1).-
Exercise valve part stroke (in the direction required to i
QP.
fulfill its safety-related function) #or operability every three.(3) months.
Exercise valve ' full stroke (to the position required to QCS fulfill its safety-related function) for operability during cold shutdowns.
If applicable, take stroke time measurements and compare to the stroke time limiting i
value per Section XI, Article IWV-3410 (see Note 1).
Exercise, valve part stroke (in the direction.to fulfill QPCS its safety-related function) for' operability during cold
-shutdowns.
Exercise valve full stroke (to the position required to QR fulfill its safety-related function) for operability during. refueling.
If applicabic, take stroke time measurements and compare to the stroke time limiting value per Section XI, Article '1WV-3410 (see Note 1).
QPR Exercise valve part stroke (in the direction required to fulfill its safety-related function) for operability during refueling.
L l.-
L______________.______._
P1 Visually observe,' at least once every two years. actual' valve position to confirm that. remote valve. position indications accurantely reflect valve. operation.
Remove actuator power from valves with fail-safe FT l
actuators to confirm that.the valve travels'to it, fail-safe position every three (3) months.
Leak test valve per Section XI, Article IWV-3420, or LT applicable relief request.
LLRT Leak test valve in conformance with the criteria sp9cified in Appendix J of 10CFR50.
SRV Test safety and relief valves ~per Section XI, Article j
IWV-3510.
'FTCS Remove actuator power from valves with fail-safe actuators to confirm that the valve travels'to its fail-safe position during cold shutdowns.
I Disassemble, Inspect, and Manually Stroke at time DET-
. interval stated applicabic relief request.
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TABLE IWV-2 SAFETY / RELIEF VALVE SETPOINTS 4
I' L _<
1_.
TABLE IWV,
ShFETY/ RELIEF VALVE SETPOINTS
-i Service' Valve No.
M Set' point (Tol.)
Safety' Injection Piping 2-SI-007 1" Re1
-2735 psig (!2%)
- Safety Injection Tanks 2-SI-211 1" Re1 250 psig (12%)
2-S1-221 1".Re1 250;psig (!2%)
2-SI-231 1".Re1 250 psig (12%).
2-SI-241 1" Re1 250 psig (12%)'
.75 Re1 1750 psig (12%)
MPSI Header A Relief-2-SI-417 1 Re1 2735 psig (12%)
.75 Re1 500 psig (!2%)
l
~ SIT-Test:Line Relief 2-SI-466 1.5 Re1 560 psig.(12%)-
- Shutdown Cooling Suction Relief.
2-SI-468
_1.5 Re1 300 psig_(12%)
l' Shutdown Cooling Suction Relief-2-SI-469 1"
300 psig (12%)
Pressurizer Relief 2-RC-200 2.5 RV 2500 psia (11%)-
Pressurizer Relief 2-RC-201 2.5 RV 2500 psia (11%).
Pressurizer POR Valves 2-RC-402 2.5" Gate 450 psig (12%)
(sol. op.)
l 2-RC-404 2.5" Gate' 450 psig (!2%)
L
-(sol. op.). 2735 psig (t2%)
j Charging Pump.A Relief 2-CH-326
.75 Re1 Charging Pump B Relief 2-CH-325
.75 Re1 2735 psig ( 2%)
Charging Pump C Relief 2-CH-324
.75 Re1 2735 psig (!2%)
Main Steam Header B Relief 2-MS-239 6" Re1 1050 psia (t1%)-
2-MS-240-6" Re1 1045 psia ( 1%)
2-MS-241 6" Re1 1025 psia (t1%)
2-MS-242 6" Re1 1005 psia (11%)
2-MS-243 6" Re1 1050 psia (11%)
2-MS-244 6" Re1 1035 psia (i1%)
2-MS-245 6" Re1 1015 psia (11%)
l 2-MS-246 6" Re1 1000 psia ( 1%)
}
Main Steam Header A Relief 2-MS-247-6" Re1 1000 psia (11%)-
2-MS-248 6" Re1 1050 psia (11%)
2-MS-249 6" Re1 1015 psia (t1%)
2-MS-250 6" Rc1 1045 psia ( 1%)
i 2-MS-251 6" Re1 1035 psia ( 1%)-
2-MS-252 6" Re1 1025 psia (11%)
2-MS-253 6" Re1 1050 psia (11%)
2-MS-254 6" Re1 1005 psia (t.%)
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RELIEF REQUEST l
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4
' MILLSTONE' NUCLEAR POWER STATION. UNIT'NO. 2' SECOND TEN-YEAR INTERVAL-
> Relief f rom In-Service Testing-Requirements Relief Request:
RR-lWV-1 IWV, l-lp Main Steam.(MISV)1 Isolation. Check. Valves For Steam Generators 2-MS-64A and 2-MS-64B-su u-i,; Component' Identification:
'ASME' Code Class:
2 LIWV 2200 Valve Categories: B'and C
-Valve Function:
To stop flow from steam generators following steam line rupture downstream of valve.
Code Requirement:
)
Paragraph IWV-3400 requires that check valves be exercised to the position required to fulfill their function and fail tested
]
quarterly.
Code Relief Requested:
- Relief is requested ~ from performing-the full stroke test during plant operation:
Basis for Relief:
Full stroke testing of these valves would require plant shutdown.
I Prop'osed Alternative Testing:
Part stroke exercise for these: valves every three_ months and full stroke exercise, fail test, and measure stroke time during cold shutdown.
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4
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i MILLSTONE NUCLEAR POWER STATION UNIT N00 2 SECOND TEN-YEAR INTERVAL Relief f rom In-Service Testing Requirements Relief Request:
RR-IWV-2 l
Main Steam Isolation Bypass Valves For Steam Generators 2-MS-65A and 2-MS-65B Component Identification:
ASME Code Class:
2 IWV 2200 Valve Category:
B Valve Functica:
Start up bypass valve around main steam isolation valve. Valve is normally closed during plant operation.
)
Code Requirement:
Paragraph IWV-3412 requires that the. valves shall be exercised for operability and measure stroke time every three months.
Code Relief Requested:
Relief is requested from performing the full stroke test during plant operation.
Basis for Relief:
Valves are normally closed and not required to change position i
during plant operation.
Failure of one of these valves in the open position during exercise would jeopardize the ability to stop steam flow in the event of downstream rupture.
These valves are used to bypass the Main Steam Isolation Valves (MSIV) during plant startup to allow controlled piping varmup and equalization of pressure prior to opening the MSIV's.
Once the MISV's are opened, these valves are shut by plant operating procedure and remain shut during normal plant operation.
During plant startup, while the valves are open, a Main Steam Isolation Signal vill close the valve automatically. This signal does not cause any valve action during periods when the valves are s!.a t.
During any test, there exists a finite probability that one of the valves vill malfunction.
If these valves are opened for test during reactor operation and malfunction they could remain open.
Alowing these valves to remain open would provide a 3" bypass line around the MSIV to remain open if piping downstream of the MSIV ruptured, thus precluding complete flow interruption and intefering with the function of the Main Steam Isolation Signal.
In this
i NILLSTONE NUCLEAR POWER STATION UNIT N0'. 2 l
SECOND TEN-YEAR INTERVAL Relief' from In-Service Testing Requirements' instance,' plant' shutdown and.cooldown could be' required to repair the valve.
,These valves'are only opened during startup.from cold shutdown.
Testing the. valves during' cold shutdown and refuelings will provide adequate assurance that the valve ~will be operable during the.
period it will be open.
Proposed Alternative Testing:
i Full s'roke exercise and measure stroke time during cold shutdown.
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RR-IWV-2.2 L-________________________
i
MILLSTONE NUCLEAR POWER STATION UNIT NO. 2 SECOND TEN-YEAR INTERV AL 1
Relief from In-Service Testing Requirements Relief Request: RR-IWV,3 Containment Spray Header Check Valves 2-CS-SA and 2-CS-5B Component Identification:
ASME Code Class:
2 IWV.2200 Valve Category: C Valve Function:
Check valves in containment spray headers, inside containment.
Code Requirement:
)
Article IWV-3000 requires that the valves be exercised (full stroke) quarterly.
l, Code Relief Requested:
Relief is requested from performing the full stroke test quarterly:
Basis for Relief:
Valve operation cannot be verified during reactor operation since the valves are inaccessible during plant operation. To verify movement of these valves, air is admitted upstream and valve motion monitored audibly. Water cannot be used for this test since containment wetting would result.
This valve functions to allow flow to the spray header following a Containment Spray Actuation System event.
It also functions as the inside containment isolation valve on a line which is open to the containment atmosphere and penetrates the containment boundary.
l The valve is installed in a vertical pipe leading to the j
containment spray nozzles.
The disk rests naturally in the closed i
position. Water, the normal fluid in the system, cannot be used to l
test the valve in the open direction since massive containment l
vetting would occur it full flow was passed through the valve.
l Northeast Nuclear Energy Company considers, based on experience, that admitting air upstream of the valve and verifying that the valve moves promptly to the open position by noting the sound of I
the valve disk impacting the disk stop provides adequate asserance l
that the valve moves freely and will move to the full open position when s.tbjected to water flow.
MILLSTONE NUCLEAR POWER STATION UNIT NO.'2-SECOND TEN-YEAR INTERVAL Relief f rom In-Service Testing. Requirements '
Since no water test will effectively test'the operation of the valve, the usual alternative would beuto disassemble the valve'and-verify: manually that the disk travels asLrequired. Northeast 0
Nuclear. Energy Company considers an air test-which demonstrates l
full, free movement offthe valve. disk substantially.more. effective in demonstrating actual operability than disassembly of the valve.
Proposed i.iternative Testing:1 Velve will be full stroke exercised during extended (greater than three weeks) cold shutdowns and at refueling outages.
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RR-IWV-3.2
f
-(-.
MILLSTONE NUCLEAR POWER STATION UNIT NO. 2 SECOND TEN-YEAR INTERVAL Relief from In-Service Testing Requirements Relief Request:
RR-IWV-4 l-h Containment Spray Refueling Water Storage Tank Header (RWST) Check
~
Valves 2-CS-14A and 2-CS-14B Component Identification:
ASME Code Class:
2
-IWV 2200 Valve Category:
C Valve Function:'
Check valvesito prevent-backflow from safety injection suction header-to the RWST.
l Code Requirement:
Article IWV-3000 requires that this valve be exercised (full stroke) every three months.
Code Relief Requested:
Relief is requested from performing the required exercised.(full stroke) test every three months during plant operation.
j 1
Basis for Relief.
Valve cannot be full stroke exercised during reactor operation i
since the only full flow path is into the reactor coolant system.
Valve cannot be full stroked during cold shutdown since over-pressurization would result.
Proposed Alternative Testing:-
Valve shall be part stroke exercised quar *erly and full stroke cycrcised at each refueling.
1 5
MILLSTONE NUCLEAR POWER STATION UNIT NO. 2 SECOND TEN-YEAR INTERVAL Relief from In-Service Testing Requirements Relief Request:
RR-1WV-5 Containment Spray, Containment Sump Outlet Header Check Valves 2-CS-15A and 2-CS-15B Component Identification:
ASME Code Class:
2 IWV 2200 Valve Category: C Valve Function:
Check valve to prevent backflow into containment sump.
Code Requirement.:
Article 1WV-3000 requires that this valve be exercised to open position every three months.
Code Relief Requested:
P.elief is requested from exercising the above-listed valves to the open position every three months.
Basis for Relief:
These valves cannot be stroke tested using system fluids. To attempt to do so would require filling the containment to design post-accident water depth and drawing water from the containment with safety-related pumps. This would result in massive spread of radioactive contamination. The proposed alternative, i.e.,
disassembly, visual examination, and manually stroking the valve through full travel - requires that the safety injection suction header be isolated and drained. This creates approximately 15,000 gallons of radioactive liquid waste.
These valves sit in a carefully controlled. water environment. They are not subject to wear or other damage mechanisms. When the valves were first visually examined in 1981 after more than seven years of " service" there was no evidence of corrosion or wear which could impact the operation or integrity of the valve. Northeast Nucicar Energy Company considers the more frequent disassembly and inspection of these valves to have a higher potential fer adverse impact than the proposed examination schedule.
Since no increase in reliability or safety would result from increased examinations.
the costs and personnel exposure as well as the generation of radioactive liquid and solid waste associated with such tests, are considered unwarranted.
If degradation is found in the valve examined the other similar valve would also be examined prior to reactor startup.
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MILLSTONE NUCLEAR POWER STATION UNIT NO. 2 SECOND TEN-YEAR INTERVAL l
Relief f rom In-Service Testing Requirements Proposed Alternative Testing:
The valve will be part stroke exercised every three months.
One I
valve vill be disassembled, Visually Examined, and stroked through full travel each 40-month period.
1 RR-IWV-5.2
+
M.LSTONE NUCLEAR POWER STATION UNIT NO. 2 SEC0hT TEN-YEAR INTERVAL Relief from In-Service Testing Requirements
, Relief Request:
RR-IWV-6 High Pressure Safety Injection (HPSI) Check Valves j
2-SI-008, 009, 010, 011, 012, 113, 123, 133, 143, 401, 405,
)
410, 414, and 427 Comyonent Identification:
ASME Code Class:
2 IWV 2200 Valve Category:
B Valve Function:
Variou,s check valves in HPSI flow paths to prevent backflow.
Code Requirement:
IWV-3000 requires these valves to be exercised (full stroke) every three months.
Code Relief Requested:
Relief is requested from performing tha required exercising (full stroke) during reactor operation and cold shutdowns.
Basis for Relief:
I I
l Valves cannot be full atroke exercised during reactor operations i
since the only full flow path is into the reactor coolant :'/ s t em.
HPSI pumps do not have sufficient discharge pressure (1.200 psi) to overcor,e reactor coolant pressure (2,250 psi). Valves cannet be full stroke exercised during cold shutdown, since full HPSI flow into the reactor could result in reactor coolant system overpres-surization, Proposed Alternative Testing:
Design flow tents will be conducted during reactor refueling with the reactor head removed. These tests are conducted while filling the reactc. pool chvity and effectively demonstrate that these check valves do operate properly. Partial stroke exercising will be donc quarterly.
l MILLSTONE NUCLEAR F0WER STATION UNIT NO. 2 SECOND TEN-YEAR INTER'?AL Relief from In-Service Testing Requirements Relief Request:
RR-IWV-7 Low-Pressure Safety' Injection Check Valves y
2-51-114, 124, 134, 144, 434, and 446 Component Identification:
ASME Code Class:
2 IWV 2200 Valve Category:
C Valve Function:
Various check valves in the LPS1 flow paths to prevent backflow.
Code Requirement:
IWV-3000 requires these valves to be exercised (full stroke every three months).
Code Relief Requested:
h Relief is requested from performing the required exercising (full stroke cn; part stroke) during power operation, y
Basis for Relief:
Valves cannot be full or part stroke exercised during power opera-tion because LPSI pumps cannot overcome SIT pressure downstream of the 2-S!-706 series valves. Pump discharge check valve exercising during operation would require extensive flow path realignment, thus rendering the normal LPSI flow path inoperative for extended periods.
Proposed Alternative Testing:
i These check valves are full stroke exercised at cold shutdown l
during the shutdown cooling mode.
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.g MILLSTONE NUCLEAR POWER STATION UNIT NO. 2 SECOND TEN-YEAR INTERVAL.
Relief from In-Service Testing Requirements j
Relief Request: 'RR-IWV '
i Safety-Injection System Valves 2-SI-215, 225, 235, and 245 Component Identification:
'ASME Code Class:
1 IWV 2200 Valve Category: C
-Valve Function:
Prevent backflow into the safety injection tank. All rapid 1
discharge of the sefety injection tank in'the event of a
' loss-of-coolant accident.
Cod,e Requirerr.ent:
IWV 3522 requires that these check valves be exercised to the
. position required to fulfill their function quarterly during plant
, operation.-
Code Relief Requested:
Relief is required from quarterly test, testing during cold shutdown','and full' stroke testing during each refueling.
i B, asis for Relief:
Valves cannot be fu11' stroke exercised during reactor operation or
]
cold shutdown since no flow path kxists which can accept full flow.
Valves cannot be part stroke tested during reactor operation since failure of the test line isolation valve to shut would result in loss of safety injection tank icvel and consequent plant shutdown.
Further, if the valve f ailed to rescat only single valve isolation would exist between the reactor coolant system and the low pressure safety injection tank. The flow rates available through the small
-l diameter test line would not result in signficant operation of the valves during operation or cold shutdown.
P,,roposed Alternative Testing:
i Part stroke at high flow rates dt. ring each refueling. The test flow rate, while less the full design flow will be sufficient to fully open the valve. This flow rate is adequate to identify significant maloperation of the valve.
In addition one valve will I
be disassembled and inspected for operabili.y each 40-month period in conjunction with the required internal visual examination of the i
- a...
pressure boundary.
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i MILLSTONE NUCLEAR POWER STATION UNIT NO. 2 SECOND TEN-YEAR INTtRVAL Relief from In-Service Testing Requirements Relief Request:
RR-IWV-9 Safety Injection System Valves 2-SI-217, 227, 237, and 247 Component Identification:
ASME Code Class:
1 IWV 2200 Valse Category: C Valve Function:
Prevent backflow into the safety iniection header. Allow rapid discharge of the safety injection tank and injection of water to the reactor coolant system in the event of a loss-of-coolant accident.
Code Requirement:
IWV 3522 requires that these check valves be exercised to the position required to fulfill their function quarterly during plant operation.
Code Relief Requested:
Relief is requested from quarterly test, testing during cold shutdown, and full stroke testing during each refueling.
i Basis for Relief:
Valves cannot be full stroke exercised during reactor operation or cold shutdown since there is no pressure source able to overcome Reactor Coolant System Pressure which can fully open the valves.
Valves cannot be par". stroke tested during reactor operation since injection of cold water would result in an unacceptabic thermal shock to the safety injection nozzlc. Valves cannot be full stroke tested during cold shutdown and refueling since there is no source of water abic to provide full design flow.
Disassembly beyond that proposed in Alternative Testing would result in unnecessary personnel radiation exposure. These valves are in High Radiation Areas (general area dose rates in excess of 100 mrem / hour) and have contact radiation levels of several hundred mrem / hour.
Previous inspections have resulted in total personnel doses of 3 to 5 rem.
l Proposed Alternative Testing:
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Part stroke at high flow rates during each refueling. The test I
flow rate, while less than full design flow will be sufficient to l
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MILLSTONE NUCLEAR POWER STATION UNIT NO. 2 SECOND TEN-YEAR INTERVAL Relief from In-Service Testing Requirements
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fully open the valve. This flow rate is adequate to identify significant maloperation of the valve.
In addition one valve vill be disassetabled and inspected for operability each 40-month period in conjunction with the required internal visual examination of the pressure boundary.
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f RR -IW-9. 2
l MILLSTONE NUCLEAR POWER STATION UNIT NO. 2 SECOND TEN-YEAR INTERVAL R
Relief from In-Service Testing Requirements l.
r_
Relief Request: RR-IWV-10 Shutdown Cooling. System Isolation Gate Valve 2-SI-652 Component Identification:
ASME' Code Class:. 1
.IWV 2200 Valve Category: B
, Valve-Function:
To isolate' shutdown' cooling system piping from reactor coolant system.-
Code Requirement:-
-IWV-3000 requires that this valve be exercised and stroke time
~
measured.every three months.
Code Relief Requested:
Relief is. requested from performing the required exercise and measurement during plant operation every three months.
Basis for Relief:
Valves are locked closed when reactor coolant system pressure exceeds 300 psig to protect the low-pressure shutdown. cooling piping.. Valve exercise would require violation of plant' inter-locks.
~ Proposed Alternative Testing:
l Exercise and-measure stroke time during cold shutdown when reactor coolant system' pressure is less than 300 psig.
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MILLSTONE NUCLEAR POWER STATION UNIT NO. 2 SECOND TEN-YEAR INTERVAL Relief from In-Service Testing Requirements Relief Request: RR-IWV-11 Safety Injection System Isolation Globe Valve 2-SI-659 and 2-S1-660 Component Identification:
)
ASME Code Class:
2 IWV 2200 Valve Category: B Valve Function:
Isolate minimum flow recirculation piping from refueling water storag,e tank when safety injection system is operating in contain-ment sump recirculation mode.
Code Requirement:
IWV-3000 requires that this valve be exercised, fail tested, and stroFo time measured every three months.
Code Relief Requested:
Relief is requested from performing the required exercise and measurement every three months during reactor operation.
Basis for Relief:
Valve is required by plant technical specification to be open with valve operator power removed to provide a recirculation flow path during reactor operation.
Proposed Alternative Testing:
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Exercise (full stroke), fail test, and measure stroke time during cold shutdown.
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' MILLSTONE NUCLEAR POWER STATION UNIT NO. 2 l
SECOND TEN-YEAR INTERVAL Relief from In-Service Testing Requirements t
Relief Request:
RR-1WV-12 Safety injection HPSI/LPSI Check Valves 2-SI-706A, 706B, 706C, and 706D Component Identification:
ASME Code Class:
1 IWV 2200 Valve Category: C i
Valve Function:
Inside containment check valves in the HPSI/LPSI flow path.
l Code Requirement:
IWV-3000 requires that these valves be exercised (full stroke) every three months.
Code Relief Requested:
Relief is requested from performing the required exercise test during plant operation.
Basis for Relief:
Valves cannot be full stroked during operation because the only full flow path is into the reactor coolant system.
Proposed Alternative Testing:
Valves will be part stroked quarterly with the HPSI system and will i
be full stroked at cold shutdown during the shutdown cooling mode.
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MILLSTONE NUCLEAR p0WER STATION UNIT NO. 2 SECOND TEN-YEAR INTERVAL Relief from In-Service Testing Requirements Relief Request:
RR-IWV-13 Feedwater System Check Valves 2-FW-SA and 2-FW-SB Component Identification:
ASME Code Class:
2
)
IWV 2200 Valve Category:
B and C d
Valve Function:
To prevent backflow in main feed piping to steam generators.
Code Requirement:
IWV-3000 requires that thece valves be exercised (full stroke) for operability and stroke time measured ever;, three months. Test for fail safe operation.
Code Relief Requested:
Relief is requested from performing the required exercise, stroke time measurement, and fail safe test every three uonths during plant operation.
Basis for Relief:
Valve exercise during plant operation would requirc stopping feed flow to the steam generator with consequent plant shutdown.
Valve has no part stroke capability. Valve operator is not connected to obturator.
Obturator cannot be exercised during cold shutdown or refueling, j
These valves have no safety function in the open position.
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While the valve will normally close during shutdown from power 1
operation, and valve closure can be visually determined, there is l
I no practical octhod to meet the Code requirement to " prove that the disk travels to the seat promptly on cessation or reversal of flow." Deliberate, abrupt cessation or reversal of flow in the 18-inch diameter feed line is not considered prudent.
Such action l
I could result in system damage or undesirable trancients in steam generator icvel, i
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Northeast Nuclear Energy Company experience indicates that thesc l
valves are not subject to rapid wear. The occurred as a result of l
a valve modification which decreased the internal cicarances and caused restriction in valve movement.
Examining one valve each l
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MILLSTONE NUCLEAR POWER STATION UNIT NO. 2 SECOND TEN-YEAR INTERVAL Relief from In-Service Testing Requirements refueling outage is considered adequate to assure the operability of these valves.
Proposed Alternative Testing:
Exercise valve operator, measure stroke time, and fail-safe test during cold shutdown. Disassemble one valve each refueling outage to verify obturator freedom of movement.
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I RR-IWV-13.2
- 8 1-Ni l1.
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MILLSTONE NUCLEAR POWER STATION UNIT NO. 2 SECOND TEN-YEAR INTERVAL Relief from.In-Service Testing Requirements-
, Relief Request: -RR-IWV-14
[
Auxiliary Feedwater System Check Valve 2-FW-7, 8A and 8B Component Identification:
ASME Code Class:
3 IWV.2200 Valve Category:.C Valve Function:
-To prevent backflow through auxiliary feed pump during operation of
~other auxiliary feed pumps.
Code Requirement:
IWV-3000 requires that this valve be exercised every three months g:p for' operability.
' Code Relief Requested:
Relief is requested from performing the required exercise test every three months during plant operation.
' Basis for Relief:
Operation of this valve would require establishing flow through the auxiliary feedlines to the steam generator.
Introduction of this cold water could result in steam generator level instability and/or
' undesirable thermal transients to the feed nozzles.
Proposed Alternative Testing:
r Exercise valve for operability during cold shutdown.
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MILLSTONE NUCLEAR POWER STATION UNIT NO. 2 SECOND TEN-YEAR INTERVAL Relief: from In-Service Testing Requirements Relief Request:
RR-IWV-15 Auxiliary Feedwater System Check. Valves 2-FW-12A snd 2-FW-12B Component Identification:
'ASME Code Class:
2 IWV 2200 Valve Category: B and C Valve Function:
.To prevent backflow in auxiliary feedwater lines to steam generators.
Code Requirement:
IWV-30C0 requires that these valves be exercised (full stroke) for operability and stroke time measured every three months. Test for fail-safe operation.
Code Relief Requested:
Relief is requested from performing the required exercise, stroke time measurement, and fail-safe' test every three months during plant operation.
Basis for Relief:
Valve operator exercise without an auxiliary feed system flow will not result in actual valve exercise.
Initiating auxiliary feed-water flow during plant operation could result in steam generator level instability and/or undesirable thermal transients to the feed nozzles.
Proposed Alternative Testing:
brercise valve for operability, measure stroke time, and fail-safe test during cold shutdown.
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MILLSTONE NUCLEAR POWER STATION UNIT NO. 2 1
SECOND TEN-YEAR INTERVAL Relief from In-Service Testing Requirements i
{
1 Relief Request: RR-1WV-16 Reactor Building Closed Cooling Water Check Valves 2-RB-30.1A, 30.1B, 37.2A and 37.2B Component Identification:
ASME Code Class:
2 IWV 2200 Valve Category: B Valve Function:
To isolate misec11ancous containment heat loads.
Code Requirement:-
IWV-3000 requires that these valves be exercised (full stroke) and stroke time measured every three months.
Code Relief Requested:
Relief is requested from performing the required exercise and stroke time measurement during pitnt operation every three months.
Basis for Relief:
Exercising these valves would result in interrupting cooling water to the reactor coolant pump thermal barriers and oil coolers, as i
vell as other loads required during reactor operation. Valve design precludes part stroke exercising.
Proposed Alternative Testing:
Valve vill be full stroke exercised on cold shutdown when reactor coolant pumps are not running.
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MILLSTONE NUCLEAR POWER STATION UNIT NO. 2 SECOND TEN-YEAR INTERVAL Relief from In-Service Testing Requirements Relief Request:
RR-IW-17 Chemical and Volume Control Check Valve 2-CH-177 and 2-CH-190 Component Identification:
ASME Code Class:
2 IWV 2200 Valve Category:
C Valve Function:
Boric acid pumps discharge to charging header suction nonreturn l
Code Requirement:
IWV-3000 requires that this valve be exercised to the full open j
position every three months.
~
Code Relief Requested:
Relief is requested from performing the required exercise to full open position every three months, Basis for Relief:
)
i Operation of this valve during normal plant operation would allow concentrated boric acid to flow directly to the charging pump suction header, resulting in a rapid reduction in reactor power.
Proposed Alternative Testing:
Exercise the check valve to the full open position every cold shutdown.
[
MILLSTONE NUCLEAR POWER STATION UNIT NO. 2 SECOND TEN-YEAR INTERVAL Relief from In-Service Testing Requirem1nts Relief Request: RR-IWV-18 Chemical and Volume Control System Valve 2-CH-501 Component Identification:
3 ASME Code Class:
2 IWV 2200 Valve Category: B Valve Function:
To isolate volume control tank from charging pump suction upon safety injection actuation signal.
Code Requirement:
IWV-3000 requires that this valve be exercised (full stroke) and
]
the stroke time measured every three months.
)
Code Relief Requested:
l Relief is requested from performing the required exercise and stro'ke time measurement every three months during plant operation.
Basis for Relief:
Exercising this valve would require interruption of charging flow 4
vith the attendant, undesirable, thermal transient on the regenera-tive heat exchanger.
If an alternate charging pump suction source-were utilized, an undesirabic reactor coolant system boron concen-tration transient could result.
' Proposed Alternative Testing:
Exercise full stroke and measure stroke time during cold shutdown.
MILLSTONE NUCLEAR POWER STATION UNIT NO. 2 SECOND TEN-YEAR INTERVAL Relief from In-Service Testing Requirements Relief Request:
RR-IWV-19 Chemical and Volume Control Clobe Valve 2-CH-515 l
I Component Identification:
ASME Code Class:
2 IWV 2200 Valve Category: B i
Valve Function:
To isolate reactor coolant system charging and letdown lines on i
safety injection actuation s'ignal.
Code Requirement:
IWV-3000 requires that this valve-be exercised (full stroke), fail tested, and the stroke time measured every three months.
Code Relief Requested:
Relief is requested from performing the required exercise and stroke time measurement every three months during plant operation.
basis for Relief:
Operation of this valve during plant operation would cause undesir-abic thermal transients of approximately 400* on the regenerative heat exchanger. This ccmponent has a limited number of design thermal transients. Valve design precludes part stroke testing.
Proposed Alternative Testing:
Exercise full utroke, fail test, and measure stroke time during cold shutdown, i
MILLSTONZ NUCLEAR POWER STATION UNIT NO. 2 SECOND TEN-YEAR INTERVAL Relief from In-Service Testing Requirements Relief Request:
RR-IWV-20 Chemical and Volume Control Globe Valve 2-CH-431 and 2-CH-517 Component Identification:
ASME Code Class:
1
.IWV 2200 Valve Category:
B Valve Function:
To provide flow to pressurizer vapor space during depressurization.
Code Requirement:
IWV-3000 requires that this valve be exercised (full stroke), fail tested, and the stroke time measured every three months.
Code Relief Requested:
Relief is requested from performing the required exercise and stroke measurement every three months during plant operations.
J Basis for Relief:
Valve exerciso during reactor operation could cause loss of reactor coolant system pressure control with consequent plant shutdown and/or excessive thermal transients on the pressurizer spray
- piping, i
Proposed Alternative Testing:
Exercise (full stroke), fail test, and measure stroke time during cold shutdown.
l MILLSTONE NUCLEAR POWER STATION UNIT NO. 2 SECOND TEN-YEAR INTERVAL l
Relief from In-Service Testing Requirements 9
, Relief Request:
RR-IWV-21 Reactor Coolant System Venting Solenoid Valves 2-RC-414, 415, 416, 417, 422, 423, 424, and 424 Component Identification:
ASME Code Class:
1 i
IWV 2200 Valve Category:
B j
Valve Function:
1 To provide venting of reactor coolant system.
Code Requirement:
IWV-3000 requires that these valves be exercised (full open posi-tion) every three months.
Code Relief Requested:
Relief is requested from performing the required exercise during plant operations every three months.
Basis for Relief:
These valves provide the two valve boundary between the Reactor Coolant System and the containment atmosphere. They are locked closed during reactor operation. Operation of one of these valves could result in a coolant leak or loss-of-coolant accident if the other series valve leaked or had failed. Northeast Nuclear Energy Company considers it imprudent to violate the two valve barrier i
solely to verify operability of these valves.
Proposed Alternative Testing:
Exercise full stroke during cold shutdowns.
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MILLSTONE NUCLEAR POWER STATION UNIT NO. 2 SECOtiD TEN-YEAR INTERVAL i
Relief from In-Service Testing Requirements Relief Request: Pa-IW-2 2 Containment Isolation Globe Valve 2-CH-089 Component Identification:
ASME Code Class:
2 l
IW 2200 Valve Category: A Valve Function:
To provide containment isolation for reactor coulant system letdown i
piping,on containment isolation signal.
Code Requirement:
IW-3000 requires that this valve be exercised (full strcke), f ail tested, and the stroke time measured every three months.
Code Relief Requested:
l Relief is requested from performing the required exercise, fail test, and stroke measurement every three months during plant operations.
Basis for Relief:
Operation of this valve during plant operation would cause undesir-able thermal transients on the regenerative heat exchanger. This j
component has a limited number of design thermal transients.
Proposed Alternative Testing:
)
Exercise (full stroke), fail test, and measure stroke time during cold shutdowns.
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MILLSTONE UUCLEAR POWER STATION UNIT NO. 2 SECOND TEN-YEAR INTERVAL Relief from In-Service Testing Requirements i
Relief' Request: 'RR-IWV-23 Containment Isolation Globe Valves 2-CH-198,'2-CH-505 and 506 Component Identification:
ASME Code Class:
2 IWV 2200 Valve Category: A Valve Function:
To isolate reactor coolant pump seal leak-off line at containment penetration.
Code Requirement:
.IWV-3000 requires that these valves be exercised, fail tested, and the stroke times measured every three months.
Code Relief Requested:'
\\
Relief is requested from performing the required exercise, stroke
-j time measurement and failure testing during~ reactor coolant pump operation.
Basis for Relief:
These valves are required to be open anytime the reactor coolant valves could result in seal failure.
"j pumps are operating to allow seal leak-off flow.
Closing these Proposed Alternative Testing:
)
Exercise, measure stroke time, and fail test during cold shutdown j
when reactor coolant pumps are secured.
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MILLSTONE NUCLEAR POWER STATION UNIT NO. 2
- SECOND TEN-YEAR INTERVAL Relief from In-Service Testing Requirements
. Relief Request: RR-IWV-24 Containment Isolation Globe Valve 2-CH-516 l
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Component Identification:
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l ASME Code C1 css:
2 IWV 2200 Valve Category: A Valve Function:
To isolate reactor coolant system letdown line on containment isolation signal.
Code Requirement:
)
IWV-3000 requires that this valve be exercised (full stroke) and the stroke time measured every three months.
Code Relief Requested:
Relief is requested from performing the required exercise, fail test, and stroke time measurement every three months during plant operation.
Basis for Relief:
Operation of this valve during plant operation vould cause undesir-able thermal transients on the regenerative heat exchanger. This component has a limited number of design thermal transients.
Proposed Alternative Tasting:
Exercise (full stroke), f ail test, and measure stroke time during cold shutdown.
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f MILLSTONE NUCLEAR POWER STATION UNIT NO. 2
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SECOND TEN-YEAR INTERVAL Relief from In-Service Testing Requirements Relief Request: RR-IWV-25 Containment Isolation Gate Valve 2-SI-651 Component Identification:
ASME Code Class:
1 IWV 2200 Valve Category:
A Valve Function:
To isolate shutdown cooling system piping from reactor coolant system.
Code Requirement:
IWV-3000 requires that this valve be exercised and the stroke time measured every three months.
Code Relief Requested:
Relief is requested from performing the required exercise and stroke time measurement during plant operation every three months.
Basis for Relief:
Valves are locked closed when reactor coolant system pressure exceeds 300 psig to protect the icv-pressure shutdown piping.
J Valve exercise vould require violation of plant interlocks.
l Proposed Alternative Testing
- Exercise and measure stroke time during cold shutdown when reactor coolant system pressure is less than 300 psig.
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l-MILLSTONE NUCLEAR POWER STATION UNIT NO. 2 i
SECOND TEN-YEAR INTERVAL Relief from In-Service Testing Requirements Relief Request: RR-1WV-26 All Class 2, Category A and A Passive (AP) Containment Isolation Valves for applicable valves, see attached list.
Component Identification:
ASME Code Class:
2 IWV 2200 Valve Categories: A and AP Valve Function:
To insure containment integrity in event of requirements to i
isolate.
Code Requirement:
IWV-3424 requires valve seat leakage be determined by measuring the feed rate required to maintain pressure betwee.n two valves or j
between two seats of a gate valve, provided the total apparent leak j
rate is charged to the valve or gate valve seat being tested, and I
that the conditions required by IWV-3423 are satisfied.
q Code Relief Requested:
l Relief is requested from the requirement of IWV-3424b, that valve seat leakage, determined by measuring the feed rate required to maintain pressure between two valves, be charged to a single valve.
Relief is also requested to use an alternative test technique based on pressure decay rate between isolation valves when leakage exceeds the measurement limits of feed rate measuring devices.
Basis for Relief:
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The proposed alternative testing and alternate test technique comply with the requirements of Appendix J in 10CFR50.
l The proposed alternative test provides assurance that total containment leakage remains within limits yet allows trouble shooting to identify individual leaking valves without requiring i
quantification of leakage through a single valve, Proposed Alternative Testing:
t Leak Test Category A valves singly or in groups.
Where multiple j
valves on a single penetration are tested in a singic test. The leakage will be attributed to the penetration not to an individual valve.
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' MILLSTONE NUCLEAR POWER STATION UNIT NO. 2 SECOND TEN-YEAR INTERVAL Relief from In-Service Testing Requirements Analysis of leakage rate and establishment of maximum allowable leak rates will be based on total penetration leakage.
Analysis and corrective action will be in accordance with IWV-3426 and 3427.
Where leakage rates exceed measurement limits of feed rate measuring devices an alternative test based on pressure decay rate between isolation valves will be used.
1 RR-IRV-26.2
LIST OF APPLICABLE VALVES Valve-Class /
Valve Class /
Number Category Number Category 2-CH-429 2A 2-AC 2A 2-CH-198 2A 2-AC-51 2AP 2-CH-505 2A 2-EB-88 2A 2-RW-154 2AP 2-EB-89 2A
?-RW-232 2AP 2-EB-91 2A 2-SSP-16.1 2A 2-EB-92 2A 2-SSP-16.2 2A 2-EB-99 l
2A 2-AC-4 2AP 2-EB-100 2A 2-AC-5 2AP 2-SA-19
'2AP 2-AC-6 2AP 2-CH-506 2A 2-AC-7 2AP
)
2-CH-516 2A 2-AC-12 2A 2-CC-4.1A 2A 2-AC-15 2A 2-CS-4.1B 2A 2-AC-20 2A 2-SI-312 2A 2-MS-220A 2A 2-SI-463 2AP 2-MS-220B 2A 2-SI-709 2AP 2-GR-11.1 2A 2-MS-191A 2A 2-GR-11.2 2A 2-MS-191B 2A 2-LRR-43.1 2A 2-FMW-43 2A 2-LRR-43.2 2A 2A 2-LLR-61.1 2A 2-RC-001 2A 2-RW-21 2AP l
2-EC-002 2A 2-RW-63 2AP j
2-RC-003 2A 2-CH-517 1A 2-RC-45 2A 2-CH-518 2A 2-CH-089 2A 2-CH-519 2A 2-1A-27.1 2A 2-AC-46 2AP 2-AC-112 2AP 2-AC-114 2AP 2-AC-116 2AP 2-AC-117 2AP RR-INV-26.3
MILLSTONE NUCLEAR POWER STATION UNIT NO. 2 SECOND TEN-YEAR INTERVAL g
Relief from In-Service Testing Requirements Relief Request:- RR-IWV-27 Main Steam System Reverse Flow Check Valves 2-MS-1A and 2-MS-1B Component Identification:
ASME Code Class: None IWV 2200 Valve Category: C Valve Function:
Prevent backflow in main steam lines from steam generator in the event of main steam line rupture.
Code Requirement:
Paragraph IWV-3412 requires that valves be exercised quarterly to the position required to fulfill their function.
Code Relief Requested:
Relief is requested from exercising the valve to the closed position, in accordance with Code requirements.
Basis for Relief:
Closing this valve would require a plant shutdown.
Event with a plant shutdown there is no means to verify "that the disk travels to the seat promptly on cessation or reversal of flow."
Valve operation can be verified by observation of the counterweight but no means exist to abruptly stop flow.
Observation of normal valve operation during reduction of steam plant load provides adequate assurance that the valve is operable.
Proposed Alternative Testing:
Verify during each cold shutdown that the valve travels smoothly and completely to the closed position as steam plcnt load is
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MILLSTONE NUCLEAR POWER STATION UNIT NO. 2 SECOND TEN-YEAR INTERVAL y
Relief from In-Service Testing Requirements
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i Relief Request:
RR-IW-28
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1 2-EB-88, 2-EB-89, 2-LRR-61.1, 2-SSP-16.1, 2-0R-11.1, 2-LRR-43.1, l
2-RC-001, 2-RC-002, 2-RC-003, 2-SI-618, 2-SI-628, 2-SI-638, 2-SI-648, 2-CH-518, and 2-CH-519.
Component Identification:
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1 ASME Code Class:
1,2 IW 2200 Valve Category:
B Valve Function:
Valves 2-SI-618, 628, 638, and 648 open to allow depressurization of the safety injection header in the event of leakage through valves 2-SI-217, 227, 237, or 247.
These valves are normally shut and fail shut.
Valves 2-EB-88 and 89, 2-LRR-43.1 and 61.1, 2-SSP-16.1 provide "inside containment," containment isolation protection.
I 2-RC-001, 002, and 003 are reactor coolant sample isciation valves.
2-CH-518 and 519 are. loop charging header isolation valves.
Code Requirement:
i Paragraph IW-3415 requires that valves be tested by observing the operation of the valves upon loss of actuator power.
i Code Relief Requested:
Relief.is requested from testing the fail-safe operation of the valve quarterly.
Basis for Relief:
The valve acuator power is air. The valves are in containment and thus, inaccessible for isolating the air supply and observation during reactor operation.
A test which deenergizes the air k
solenoid valve may not adequately test valve response under loss of air pressure.
Propsoed Alternative Testing:
The fail-safe operation of the valve will be tested during cold shutdowns.
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1 MILLSTONE NUCLEAR POWER STATION UNIT NO. 2 SECOND TEN-YEAR INTERVAL-
. Relief from In-Service Testing Requirements i
Relief Request RR-IWV-29
.All power operated valves listed in the valve lists.
j Component Identification:
ASME Code Class:
1,2,3 IWV 2200 Valve Category:
A, B Valve Function As identified in valves lists.
Code Requirement Paragraph IWV-3417
"(a) If, for power operated valves, an increase in stroke time of 25 percent or more from the previous test for valves with full-stroke times greater than 10 see or 50 percent or more for valves with full-stroke times less than or equal to 10 see is observed, test frequency shall be increased to once each month until corrective action is taken, at which time the original test frequency shall be resumed.
In any case, any abnormality or erratic action shall be reported.
Code Relief:
Relief is requested from comparing present stroke times to stroke times from'the previous test.
Basis for Relief:
Use of the " previous test" stroke time does not adcquately identify slow degradation of valve performance.
For example, repeated increases in stroke time of 15 to 24 percent would not require that-the valve be considered in " Alert", with attendant additions 1 investigation and testing. The proposed alternative acceptance criteria would identify such valves and require that they be formally evaluated for acceptability or declared inoperable.
In instances where the evaluation does not result in a determination of inoperability additional or increased frequency testing may be specified to aid in evaluating valve performance. This criteria provides increased assurance that degrading valves are promptly identified and that such degradation is promptly evaluated for its impact on valve operability.
Proposed Alternative Test results shall be compared to the reference values of stroke time for each valve.
a.
Valves with reference stroke times greater than 10 second shall exhibit no more than 25 percent change in stroke time when compared to the reference value.
MfLLSTONE NUCLEAR POWER STATION UNIT NO. 2 SECOND TEN-YEAR INTERVAL Relief from In-Service Testing Requirements b.
Valves with reference stroke times less than 10 seconds shall exhibit no more than a 50 percent or 1 second (which ever is greater) change in stroke time when compared to the reference value.
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Valves with reference stroke times of less than 2 seconds l
shall not exhibit a stroke time in excess of 2 seconds.
Valves with measured stroke times which do not meet the above acceptance criteria shall be immediately retested (or declared inoperable).
Valves which can only be tested during cold shutdowns or refeuling outages shall be retested to verify compliance with the acceptance criteria or repaired before plant startup.
Evaluation of acceptable degraded performance or increased frequency tests shall not be used to allow continued operability of the valve. The cause of the originally identified degradation shall be documented in the record of the test.
If retested and the second set of data also does not meet the acceptance criteria the data shall be analyzed within 98 hours0.00113 days <br />0.0272 hours <br />1.62037e-4 weeks <br />3.7289e-5 months <br /> to verify that the new stroke time represents acceptable valve operation, or the valve shall be declared inoperable. When the evaluation indicates the deviation is acceptable, operation of the valve shall be tested monthly until it is repaired, declared inoperable or a new reference value established.
If trended test results of a valve which previously did not meet the acceptance criteria indicat the valve will exceed the limiting value of stroke time prior to the next test or that valve operation is unreliable the valve shall be declared inoperable. The evaluation shall be documented in the record of the tests. The basis for changes in reference stroke time shall be documented in the record of tests.
If the second set of data meets the acceptance criteria, the cause of the initial deviation shall be analyzed and the results documented in the record of tests.
Valves for which measured stroke times exceed limiting values for stroke times shall be immediately declared inoperable.
Valves which are declared inoperabic shall be readjusted, repaired, or replaced prior to returning the valve to service.
A test demonstrating satsif actory valve performance shall be performed prior to returning the valves to service.
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I RR-IRV-29.2 1
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MILLSTONE NUCLEAR POWER STATION UNIT NO. 2 SECOND TEN-YEAR INTERVAL Relief - f rom In-Service Testing Requirements Relief Request:
RR-IWV-30 l
Main Steam Check Valves 2-MS-4A and 4B Component Identification:
ASME Code Class:
3 IWV 2200 Valve Category:
C Valve Function:
Prevent backflow in main steam piping in the event of a pipe i
l rupture upstream of the Main Steam Isolation Valves. ' Admit steam to the turbine driven auxiliary feedwater pump when needed.
Code Requirement:
IWV 3522 requires that these check valves be exercised to the position required to fulfill their function quarterly during plant operation.
Code Relief Requested:
Relief is requested from verifying that the valve strokes fully 1
open every three months during reactor operation.
Basis For Relief:
There is no flow path available during reacter operation which will assure the valve passes full design flow.
Operation of the turbine driven auxiliary feedwater pump at design flow conditions would cause a significant thermal shock to the f eed piping, result in steam generator icvel control instability, and possible reactor trip, Part stroke operation in the open direction can be conducted in conjunction with in-service testing of the turbine driven feed pump at part load.
Proposed Alternative Testing:
1 Part stroke test the valve in the open direction quarterly. Verify valve closure after each test.
Full stroke valve open and closed prior to startup from cold shutdown.
MILLSTONE NUCLEAR POWER STATION UNIT NO. 2 SECOND TEN-YEAR INTERVAL Relief from In-Service Testing Requirements l
l Relief Request:
RR-IWV-31 f
Air Starting System Valves 2-DG-91A, 91B, 92A, 92B, 95A, 95B, 96A, 96B, 27A, and 27B i
Conponent Identification:
{
l ASME Code Class: None j
IWV 2200 Valve Category: B l
Valve Function
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Admit air to diesel engine for starting.
Code Requirement-1 Article IWV-3413(b) - The stroke time of all power operated valves j
shall'be measured to the nearest second, for stroke times 10 1
seconds or 1ess, or 10 percent of the specified limiting stroke time for full stroke times longer than 10 seconds whenever such a j
valve is full stroke tested.
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Code Relief Requested:
l Relief is requested from measuring stroke time and fail testing of
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these valves.
Basis For Relief:
1 These valves have no visible operating parts. There are no system instruments which monitor their operation. Thus there is no way to j
measure the stroke time of the valves.
Further, the actual stroke l
time of these valves is very short (less than one second) and l
measurement of stroke time would provide no realistic information I
for evaluation of valve condition.
The function of these valves is to admit starting air to the diesel engine and to stop air application when the engine is operating.
The Unit 2 Technical Specification requires that the diesel generator " starts from ambient condition and accelerates to
> 90 percent of rates speed and to > 97 percent of rated voltage in 620 seconds." If these valves do not travel full stroke, or operate slowly, the diesel will not meet the overall operability l
test. Thus reliance on this overall operability test is i
appropriate to demonstrate prompt valve operation.
The normal operation of these valves mimics the failure mode of the l
valve. Valve operation is caused by interruption of actuator l
power.
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MILLSTONE NUCLEAR POWER STATION UNIT NO. 2 l
SECOND TEN-YEAR 1NTERVAL i
Relief from In-Service Testing Requirements Proposed Alternate Testing:
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_Once per quarter each valve will be tested to assure proper i
operation by verifying the diesel generator meets the overall l
operability (starting) requirements of the Unit 2 Technical l
Specification when started using only one tank and one air start
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valve train.
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j RR-IRV-31.2 1
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-MILLSTONE NUCLEAR POWER STATION' UNIT NO. 2
'SECOND TEN-YEAR -INTERVAL 4
Relief from In-Service Testing Requirements Relief Requsst:
RR-IWV-32 Main Steam Valves 1
2-MS-190A and-190B Component Identification:
-ASME Code Class:
2 IWV 2200 Valve Category: B Valve Function:
' Provide control of steam flow to the atmosphere during cooldown.
l Provide pressure control during load reject and-trip transients to prevent lifting the steam generator relief valves.
Code Requirement:
.j
'IWV 3400 requires that these valves be exercised full stroke, fail-j
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tested, and stroke time measured.every three months during plant 1
operation.
Code Relief Requr.sted:
l Relief is requested from stroke testing, failure testing, and j
stroke time measurement every three months.
Basis For Relief:
Testing.these valves. during reactor operation would cause a reactor power excursion and consequent high power reactor trip unless the manual inlet isolation valve was shut. Closing the manual inlet isolation valve removes the protection provided by these valves. A reactor trip or turbine trip during the test could force the steam geacrator safety valves to operate.- A malfunction of a safety valve could result in an uncontrolled reactor cooldown. Deliberate reduction of the protection margin provided by these valves during the time needed to test these valves is not warranted.
Proposed Alternative Testing:
Full stroke exercise, fail test, and measure stroke time during cold shutdown.
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Docket No 50-336
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.B12724-
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5 i ATTACHMENT 2 Questions and Answers Generated From August 25 - 26,1987 Meeting
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I October 1987
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B12724/Page'2 J
October 30,1987 l
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< RESPONSES TO QUESTIONS RAISED DURING MEETING WITH NRC ON 8/25 - 8/26 Item I.A.1 - No additional Licensee response required.
c Item I.A.2 - No additional Licensee response required.
Item I.A.3 - No additional Licensee response required.
l' Item I.A.4 - The applicable relief request, RR-LWR-2.6, (previously identified as Relief Request #33 (IWV)) has been revised to reflect compliance with Articles IWV-3426 and IWV-3427.
Item 1.A.5 - The applicable relief request, RR-IWV-29, (previously identified as f
Relief Request #36 (IWV)) has been modified.
Item.l.A.6 - No additional Licensee response required.
. Item 1.B.1 - No additional Licensee response required.
Item I.C.1 - Northeast Nuclear Energy Company has been unable to verify that valves 2-MS-4A and 4B are full stroke tested by the existing test.
Relief request RR-IWV-30 addresses these valves.
. Item I.C.2 - Relief Request RR-IWV-2 contains the revised wording.
Item 1.C.3 - Additional justification for not testing these valves quarterly has been included in Relief Request RR-IWV-31.
Item I.C.4 - No additional Licensee response required.
item I.D.1 - Additional information is included in Relief Request RR-lWV-3.
Item I.D.2 - Northeast Nuclear Energy Company has concluded that valves 2-CS-I 13.l A AND 13.lB should be included in the inservice valve testing program. They have been added to the valve lists submitted with this response.
item 1.D.3.- Additional information is included in Relief Request RR-IWV-5.
Item 1.E.1 - Northeast ' Nuclear Energy Company has been unable to verify that valves 2-51-215, 225, 235, and 245 are assured of full opening under all conditions. Relief request RR-IWV S addresses these valves.
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- Attachment'2 l,
B12724/Page 2 :
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October 30,1987
. Item 1.E.2 - Northeast Nuclear Energy Company has been unable to verify that
' valves 2-S1-217, 227, 237, and 247 are assured of full opening under
- all conditions. Relief request RR-lWV-9 addresses these valves.
p Item I.E.3 -' No additional Licensee response required.
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1 Item 1.E.4 - No additional Licensee response required.
Item'I.E.5 - Additiona! information is provided in Relief Request RR-IWV-23. -
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item 1.E.6 - No additional Licensee response required.
Item I.F. 7 - Northeast Nuclear Energy Company has concluded that valves 2-SI-400, 2-CH-340 and 4-CH-440 should be included in the inservice i
valve testing: program. They have been added to the valve lists i
submitted with this response.
Item i.E.8 - Northeast Nuclear Energy Company has determined that valves 2-SI-662 and 2-51-663 have no safety function.
Item 1.F.1 - Additional information is provided in Reilef Request RR-lWV 13. -
l Item I.F.2 - No additional Licensee response required.
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Item I.F.3 - No additional Licensee response required.
item 1.F.4 - No additional Licensee response required, item 1.F.5.- No additional Licensee response required, item 1.G.1 - No additional Licensee response required.
. Item 1.H.t - The valves have been added to Relief Request R R-lWV-26 (previously Relief Request #33) as indicated.
Item I.1.1 - Northeast Nuclear Energy Company considers that these valves are Categoty C (Relief) valves under all conditions of operation. The exisiting Technical Specification and Inservice valve testing of these valves conforms to all requirements of the ASME Boiler and Pressure Vessel Code,Section XI for Category C valves.
No additional testing is required.
However, to provide additional assurance that the valves will provide low pressure overpressure protection NNECO will manually actuate each valve during the period when the pressurizer is cooled down and filled solid during a Reactor Coolant System cooldown.
These additional tests are l
reflected in the valve lists submitted with this response.
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" Attachment 2
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B12724/Page 2 ',
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October 30,1987 l
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. Item LL2
. Additionalinformation is provided in Relief Request RR-IWV-21..
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Item L3.1 No additional Licensee response required.
t' Itern 1.3.2 - Additional information is provided in Relief Request RR-lWV-28.
i itern LJ.3 - Relief Retjuest RR-IWV-26 has been revised to reference the requirements of articles IWV-3426 and 3427.
Pump Program 11.1 - The requested note has been added to the pump table.
II.2 - Relief Request RR-IWP-1 (previously Relief Request //5) includes the requested information.
e 11.3 - ' The requested notes have been added to the pump list table.
11.4 - No additional Licensee response required.
' 11.5 - No additional Licensee response required.
I II.6 - No additional Licensee response required.
Dieselgenerato s 111.1 - Emergency Diesel Generator air start aiid service water system valves are included in the valve lists. Appropriate relief requests are referenced where applicable.
Additional Area ojpwestination 111.1 - A list of accumulators which may be relied on for valve cperation i
post-LOCA have been included with the valve list. The Instrument Air check valves in the supply line to these accumulators will be tested for leak tightness each refueling.
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. OVERSIZE DOCUMENT L PAGE POLLED SEE APERTURE CARDS NUMBER OF OVERSIZE PAGES FILMED ON APERTURE' CARDS-
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APERTURE CARD /HARD COPY AVAILABLE FROM RECORD' SERVICES BRANCH FTS 492-8989
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