ML19261E236
| ML19261E236 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 06/25/1979 |
| From: | NORTHEAST UTILITIES |
| To: | |
| Shared Package | |
| ML19261E234 | List: |
| References | |
| PROC-790625, TAC-11290, TAC-8320, NUDOCS 7907050318 | |
| Download: ML19261E236 (73) | |
Text
. .
DOCKET NO. 50-336 ATTACHMENT 1 MILLSTONE NUCLEAR POWER STATION UNIT NO. 2 IN5ERVICE IfiSPECTION & TEST PROGRAM FOR PUf1PS, VALVES AND PRESSURE TESTS FOR THE 20 MONTH PERIOD APRIL 26, 1979 TO DECEMBER 26, 1980 20/ 1 9 7n .
9 0 7 0 bo36 JUNE,1979
June 1979 OPERATIONAL READIt4ESS TESTIt1G FOR PUMPS There are twenty-six pumps at Millstone Unit 2 which qualify for operational readiness testing under Subsection IWP of Section XI. Since all of these pumps are either under continuous service or. periodically surveillance tested under the plant Technical Specifications, or other existing programs, the additional data taking, formal evaluation of data and administr' tion of records and reports required by code will be implemented on April 26, ,,79, at the start of the next (second) inspection period.
Table IWP lists the pumps falling under the program, test attributes and frequency of testing.
The provisions of Subsection IWF will be adhered to insofar as installed instrumentation allows at a test frequency compatible with Subsection IWP and safe operating criteria.
To meet the vibration monitoring requirements of ASME Section XI, Subsection IWP, exception is taken to the specific vibration requirements of IWP and an alternate, more effective vibration signature analysis program as described herein, is proposed. During the inservice pump test, vibration data shall be acquired in the form of a " vibration signature" rather than a simple reading of overall vibration amplitude. The vibration signature shall consist of a plot of vibration velocity in units of inches per second, versus frequency in cycles per second, normally using a frequency range of 0 to 500 cycles per second. The vibration signature analysis approach provides a more reliable means of detecting a deterioration of pump mechanical condition, a means of diagnosing the cause of a problem and a more accurate assessment of vibration severity. The periodically acquired vibration signatures shall be compared to a baseline reference signature and analyzed for changes in amplitude peaks exceeding a threshold value. Criteria for evaluation of changes as to cause, severity and the establishment of the Alert and Required Action Ranges shall be specified in the fCIECO procedures.
Vibration measurements are made typically with an accelerometer mounted at a reference location on an equipment bearing housing and the output processed by a spectrum analyzer to product a hard copy vibration signature.
The measurmient locations to be used for monthly and baseline vibration signature data shall be established and specified by NNECO procedures.
It is the position of tHIECO that the operating status of a pump is b9st determined by plant management af ter an Engineering and Operations review of test data.
NNECO therefore requests relief from IWP-3230 (c) which requires that a pump be declared inoperative when perfornance data falls into the " required action range".
Corrective action will be further defined in performance test implementing procedures .
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BEARING TEMPERATURE REL1CF REQUEST Components All safety related pumps.
Test Requirement Measure annually the temperature of centrifugal pump bearings and main shaf t bearings of reciprocating pumps at points selected to be responsive to changes in temperature of the bearing.
Ba s i s f or Rel i e_f_
Bearing metal temperature monitoring can be effective in detecting bearing problems.
However, none of the tabulated pumps have the permanently installed temperature sensors required to measure bearing metal temperature (i.e. outer race of anti-friction bearing or babbitt lining of sleeve bearing). The annual measurement of bearing housing temperature is far less effective in detecting bearing problems than the monthly performance of vibration signature analysis being performed by NN ECO. The pumps listed in Table IWP do not have adequate design provisions to allow meaningful bearing temperatures to be taken:
. Auxiliary feedwater (3 pumps) and HPSI (3 pumps) bearing housings are water jacketed. Thus measured contact temperatures are not indicative of actual bearing metal temperature.
Boric acid (2 pumps), spent fuel pool cooling (2 pumps) and containment spray (2 punps) bearings are mounted in a massive oil filled reservoir which is in direct contact with the pumped fluid. Thus measurement of housing temperature is not indicative of bearing condition.
LPSI (2 pumps) and chilled water (2 pumps) have no pump end bearings. Driver end bearings are mounted in heavy flanges attached to the driver. The mass of this housing and the effects of motor heat on housing temperature prevent contact measurements from being indicative of bearing conditions.
Charging (3 pumps) pump bearings are recessed in a massive housing in the casing. The mass of the housing prevents contact measurements from being indicative of bearing temperature.
RBCCW (3 pumps) pump bearings have an oil reservoir and a heavy housing.
Contact measurements of housing temperature may not be indicative of actual bearing temperatures.
Service water pump bearings are under water and inaccessible.
In general, as internal bearing metal temperatures increase due to bearing over-load, improper lubrication or faulty installation, etc., much of the heat will be dissipated throughout the relatively massive housings, oil reservoir and attached casing. As a result, bearing housing temperatures will respond much less than bearing metal temperature, greatly reducing the sensitivity to detect bearing heat-up problems.
Annther important requirement to assure reliable bearing temperature monitoring is that it be continuous, not periodic. Experience indicates that failing bearings whether anti-friction type or sleeve of ten exhibit fluctuations between normal and abnormal metal temperatures. A good example is the babbitt lined sleeve bearing which wiil initially experience a rapid rise in temperature and then return to normal temperatures af ter the bearing wipes and clearances open up causing increased oil flow. The abnormal temperature rise would most probably go undetected unless continuously monitored.
The monthly vibration signature analysis conducted by NNECO will detect bearing problems at a very early stage. At the onset of a bearing problem, low level vibration will be generated at characteristic frequencies depending on the nature of the problem. The low level vibration typically amounts to less than 1% of the overall vibration amplitude and therefore cannot be detected by a simple amplitude monitoring program conforming to IWP minimum requirements. However, the low level changes in bearing distress frequencies are routinely detected in the MP-2 signa-ture analysis program and analyzed to pinpoint the cause.
Alternate Testing Record and analyze pump vibration signature monthly. Signature will be measured as velocity spectrum between zero and 500 hertz. Signatures will be evaluated using the acceptance criteria of Figure IWP-1. This monthly analysis will provide more meaningful analysis of pump bearing condition than annual measurement of bearing tempera ture.
ACCEPTANCE CRITERIA - FOR FIGURE IWP-1 Acceptable All values of the velocity signature fall within the " acceptable" range of Figure IWP-1 and all points of the velocity signature are less than 6VdB above the base-line signature.
Alert Any value of the velocity signature which falls within the " alert" range of Figure IWP-1 or any point of the velocity signature which increases by more than 6VdB.
Required Action Range Any value of the velocity signature falls which within the " required action" range of Figure IWP-1 and any point of the velocity signature increases by more than 6VdB.
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1 June 1979 OPERATIONAL READINESS TESTING FOR VALVES The attached tables include all valves in the Millstone Unit No. 2 plant which are required to be identified under Subsection IWV of ASME Section XI, Summer
'75 Addenda, as further defined in NRC Staff Guidelines and in meetings with NRC Staff Reviewers, NNECO and NUSCO personnel.
All of the valves are presently under surveillance testing requirements of Plant Technical Specifications or administratively controlled by plant regulations or requirements. In some cases, the specific requirements of IWV cannot be met due to plant design, operational requirements, or infringements on safety margins. These situations are noted, as required, and pertinent relief request, with alternate test schemes are presented. Valves which cannot be tested while the reactor is at power can, for the most part, be tested during cold shutdowns. NNEC0 has established a program to commence testing these valves within 48 hours of achieving cold shutdown conditions, and to continue as time permits on subsequent shutdowns without repeating valve test until the entire list is completed. It is the position of NNECO that the operating status of a valve including certain deviations from required stroke times is best determined by plant management af ter an Engineering and Operations review of test data. NNECO therefore requests relief from those requirements of IWV-3410 (c) (3) and IWV-3410 (g) which require an increased schedule of testing and/or the declaring of a valve out of service. Relief valve aet points will be tested in accordance with ASME PTC25.3-1976 in lieu of PTC25.2-1966 as referenced in the Summer 1975 Addenda, as the earlier version has been revised and superseded. IWV-3520 (c) Check Valve Tests - Corrective Action - requires that a valve be declared inoperative if test requirements cannot be verified within 24 hours of test performance. NNECO intends to implement this paragraph by stating corrective action in the specific valve test procedures. Unsatisfactory test results may or may not lead to an " inoperative" status, depending upon an engineering evaluation and disposition of test data by plant management.
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b e Chemical and Volume Control System 25203-26126, Sh. 8, 9 2-CH-429 2E Reactor cool and charging line 2 GA MO LO ET 2-CH-432 1C Chg. to loop 2A 2.5 CK - 0 Q Verify 0 only 2-CH-433 1C Chg. to loop 1A 2.5 CK - 0 Q Verify 0 only 2-CII-434 lE Thermal bypass 2.5 GT H LC ET 2-CH-501 2B VC tank outlet 4 GA MO O Q X QCS MT 10 Sec. 2-CH-504 2B RWST to charge pp suction 3 GA M0 C Q MT 10 Sec. 2-CH-508 2B BA Tk. B gravity feed valve 3 GA M0 C Q MT 10 Sec. 2-CH-509 2B BA Tk. A gravity feed valve 3 CA M0 C Q MT 10 Sec. 2-CH-510 2B BA pp. A recirculation 1 GL A0 0 Q MT 10 Sec. FT 2-CH-511 2B BA pp. B recirculation 1 GL A0 0 Q MT 5 Sec. FT 2-CH-512 2B VCT makeup control 4 BALL A0 C Q MT 5 Sec. FT G m w H w
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Chemical and Volume Contrcl System 25203-26126, Sh. 8, 9 2-Cll-514 2B BA pp. emerg. sply. chg. pp. suct. 3 GA M0 C Q MT 10 Sec. 2-CII-515 1B Letdown SIAS isolat. ion 3 GL A0 0 Q X QCS MT 5 Sec. PI FT X FTCS 2-CII-517 1B Aux. spray charging header 2 GL A0 C Q X QCS MT 5 Sec.
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- 1. Valve: 2-CH-177 Ca tegory/Cla ss: C-2 Function: Boric acid pumps discharge to charging header suction non-return check valve.
Test Requirement: Exercise the check valve to the full open position every 3 months. Basis for Relief: Operation of this valve during r.ormal plant operation would allow concentrated boric acid to flow directly to the charging pump suction header resulting in a rapid reduction in reactor power. Alternate Testing: Exercise the check valve to the full open position every cold shutdown.
- 2. Valve: 2-CH-190 Category / Class: C-2 Function: Boric acid storage tanks gravity feedline to charging header suction non-return check valves.
Test Requirement: Exercise the check valve to the full open position e,ery 3 months. Basis for Relief: 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. Alternate Testing: Exercise the check valve to the full open position every cold shutdown.
- 3. Valve: 2-CH-501 Ca tegorv/C lass: B-2 Function: Isolate volume control tank from charging pump suction upon Safety Injection Actuation Signal.
Test Requirement: Exercise full stroke and measure stroke time every 3 months. b d f s e SYSTD1: CHEMICAL AND VOLUME CONTROL (Cont'd) Basis for Relief: Exercising this valve would require interruption of charging flow with the attendant, undesirable, thermal transient on the regenerative heat exchanger. If an alternate charging pump suction source were utilized an undesirable Reactor Coolant System boron concentration transient could result. Alternate Testing: Exercise full stroke and measure stroke time during cold shutdown.
- 4. Valve: 2-C H-515 Ca tegory/ Class: B-2 Function: Isolate Reactor Coolant System letdown line on safety injection actuation signal.
Test Requirement: Exercise (full stroke) and measure stroke time every 3 months. Basis for Relief: Operation of this valve during plant operation would cause undesirable thermal transients or approximately 4000 on the regenerative heat exchanger. This com-ponent has a limited number of design thermal tran-sients. Valve design precludes part stroke testing. Alternate Testing: Exercise (full stroke) and measure stroke tima during cold shutdown.
- 5. Valve: 2-C H-517 Category /Cla ss: B-1 Function: Provide flow to pressurizer vapor space during depressurization.
Test Requirement: Exercisc (full stroke) and measure stroke time quarterly. Basis for Relief: Valve exercise during reactor operation could cause loss of reactor coolant system pressure control with consequent plant shutdown. Alternate Testing: Exercise (full stroke) and measure stroke time during cold shutdown. n-
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- 6. Valve: 2-C H-518 Category / Class: B-1 Function: Isolate charging to Loop 2A.
Test Requirement: Exercise (full stroke) and measure stroke time quarterly. Basis for Relief: Valve is required by Tech. Spec. to be open duririg reactor operation. Flow through valve is required for small break injection. Valves must be shut 20-30 hours af ter accident for boron precipitation con trol . Alternate Testing: Exercise (full stroke) and measure stroke time during cold shutdown.
- 7. Valve: 2-CH-519 Category /Cla ss: B-1 Function: Isolate charging to Loop 1A.
Test Requirement: Exercise (full stroke) and measure stroke tima quarterly. Basis for Relief: Valve is required by Tech. Spec. to be open during reactor operation. Flow through valve is required for small break injection. Valves must be shut 20-30 hours after accident for boron precipitation control. Alternate Testing: Exercise (full stroke) and measure stroke time during cold shutdown. oqi h ( 0l {![f[ G m E o m m x M u s
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FT X FTCS 2-FW-53 2BC Feedwater to S.G. 2 18 STOP A0 0 Q X QCS CK MT 3 Sec. FT X FTC 2-FW-7 3C Steam oux. pp. discharge 6 CK - C Q X QCS 2-FW-8A 3C Aux. pp. A discharge 4 CK - C Q X QCS 2-FW-8B 3C Aux. pp. B discharge 4 CK - C Q X QCS 2-FW-12A 2BC Aux. feedwater to S.G. 1 6 Stop A0 C Q X QCS CK MT 3 Sec. FT X FTCS 2-FV-12B 2bC Aux. feedwater to S.G. 6 Stop A0 C Q X QCS CK MT 3 Sec. FT X FTCS 2-FW-32A 3C Aux. FW pump A recire. cl.eck 1.5 CK - C Q 2-FW-32B 3C Aux. FW punp B recire. chect 1.5 CK - C Q 2-FW-33 3C Terry Aux. FW pump recire. cneck 1.5 CK - C Q
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3B Aux. FW reg. valve to No. 2 S.G. 4 GL M0 C Q 2-FW-43B MT 20 Sec. Aux. FW pump dis. cross tie 6 GA M0 C Q 2-FW-44 3B MT 10 Sec. B Aux. FJ reg. valve by-pass 6 GA H C Q 2-FW-56A 2-FW-56B 3B Aux. F4 reg. valve by-pass 6 GA H C Q
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m.- h RELIEF REQUEST BASIS SYSTD1: FEEDWATER
- 1. Valve: 2-FW-5A, SB Category: BC Class: 2 Function: Prevent backflow in main feedline to No.1 steam generator.
Test Requirement: Exercise (full stroke) for operability every three manths. Take stroke time measurements per IWV-3410. Test for fail safe operation. Basis for Relief: Valve exercise during plant operation would require stopping feed flow to the steam generator with consequent plant shutdown. Valve has no part stroke capability. Alternate Testing: Exercise valve (full stroke), measure stroke time and f ail safe test during cold shutdown.
- 2. Valve: 2-FW-7 Category: C Class: III Function: Prevent backflow through steam driven auxiliary feed pump during operation of other auxiliary feed pumps.
Test Requirement: Exercise quarterly for operability. Basis for Relief: Operation of this valve would require establishing flow through the auxiliary feed lines to the steam generator. Introduction c' 'his cold water could result in steam generator level instability and/or undesirable thermal transients to the feed nozzles. Alternate Testing: Exercise valve for operability during cold shutdown.
- 3. Valve: 2-FW-8A , 8B Category: C Class: III Function: Prevent backflow through motor driven auxiliary feed pump during operation of other auxiliary feed pumps.
Test Requirement: Exercise quarterly for operability. Basis for Relief: Operation of this valve would require establishing flow through the auxiliary feed lines to the steam generator. Introduction of this cold water could result in steam generator level instability and/or undesirable thermal 901 (j] (( transients to the feed nozzles. t t) / Alternate Testing: Exercise valve for operability during cold shutd0wn.
SYSTEP: FEEDWATER (Cont'd)
- 4. Valve: 2-FW-12A, 128 Ca tegory: BC Class: 2 Function: Prevent backflow in auxiliary feedwater line to No. I steam generator.
Test Requirement: Exercise (full stroke) for operability every three months. Take stroke time measurements per IWV-3410. Test for fail safe operation. Basis for Relief: Valve operator exercise, without a auxiliary feed systan flow will not result in actual valve exercise. Initiating auxiliary feedwater flow during plant operation could result in steam generator level instability and/or undesirable thermal transients to the feed nozzles. Alternate Testing: Exercise valve for operability, measure stroke time and fail safe test during cold shutdown.
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0 Q 2-SW-1B 3C SW pump B discharge check 24 CK - 0 Q 2-SW-lC 3C SW pump C discharge check 24 CK - 0 Q 2-SW-3.2A 3B B SW header to TBCCW IIX's 16 BFLY A0 0 Q Mf 20 Sec. FT 2-SW-3.2B 3B "A" SW header to TBCCW liX's 16 BFLY A0 0 Q MT 20 Sec. FT 2-SW-P.lA 3B A RBCCW Ifx temp. control 24 BFLY A0 0 Q MT 20 Sec. FT 2-SW-8.lB 3B B RBCCW lix temp. control 24 BFLY A0 0 Q MT 20 Sec. FT 2-SW-8.1C 35 C RBCCW IIx temp. control 24 BFLY A0 0 Q MT 20 Sec. FT 2-SW-llA 3C A discharge header check 24 CK - 0 Q
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0 Q 2-SW-13A 3C A diesel cooling discharge 8 CK - C Q 2-SW-13B 3C B diesel cooling discharge 8 CK - C Q 2-SW-89A 3B A diesel cooling temp. control 8 BFLY A0 C Q MT 20 Sec. FT 2-SW-89B 3B B diesel cooling temp. control 8 BFLY A0 C Q MT 20 Sec. FT 2-SW-102 3B A SW header to chiller X-170 2 CL A0 0 Q MT 5 Sec. FT 2-SW-104 3B B SW header to chiller X-170 2 GL A0 0 Q MT 5 Sec. FT 2-SW-192 3C Switchgear cooling coils SW disch. 4 CK - 0 Q 2-SW-197 3C Chillers service water discharge 3 CK - C Q
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0 Q 2-RW-4B 3C Pump B discharge 8 CK - 0 Q 2-RW-8 3C Return header check 10 CK - 0 Q 2-RW-10 3C Return header check 10 CK - 0 Q 2-RW-67 3C PMW return check 2 CK - C Q 2-RW-222 3C Aux. feedwater return check 2 CK - C Q
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C SRV 12 CK C X QPCS 2-SI-245 1C SIT-4 discharge - Q 12 CK C X QCS 2-SI-247 1C IIPS I , LPSI disch. to loop 2B Q 2-SI-306 2E Shutdown cooling flow control 10 BALL AO LO ET Power rc-moved 2-SI-401 2C IIPSI pump suction 8 CK - C Q X QP, QR 2-SI-402 2E IIPSI pump C suction 6 GA - LO ET 3 CK C X QP, 2-SI-405 Q 2C HPSI pump C discharge QR IIPSI pump C discharge 3 GA LO ET 2-SI-406 2E 11 2-SI-409 2C IIPSI header B relief .75 REL - C SRV 8 CK C X QP, 2-SI-410 2C IIPSI pump suction Q QR 3 CK C X QP, 2-SI-414 Q 2C IIPSI pum, B discharge QR 2-SI-415 2E IIPSI pump B discharge 3 GA II LO ET N Co 2 m
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C SRV 2-SI-421 2E IIPSI pump B recirc. 2 GL II LO ET 2-SI-422 2C IIPSI pump B recire. 2 CK - C Q 2-SI-423 2E IIPSI pump A recire. 2 GL 11 LO ET 2-SI-424 2C IIPSI pump A recire. 2 CK C Q 2-SI-425 2E IIPSI pump C recire. 2 GL II LO ET 2-SI-426 2C IIPSI pump C recire. 2 CK - C Q 2-SI-427 2C llPSI pump A discharge 3 CK - C Q X QP, QR 2-SI-428 2E IIPSI pump A discharge 3 GA II LO ET 2-SI-432 2E LPSI pump B suction 14 GA 11 LO ET 2-SI-434 2C LPSI pump B discharge 10 CK - C Q X QCS 2-SI-435 2E LPSI purup B discharge 10 GA II LO ET 2-SI-439 2C LPSI header relief .75 REL - C SRV
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C Q X QCS 2-SI-447 2E LPSI pump A discharge 10 GA H LO ET 2-SI-448 2C LPSI pump A recirc. 2 CK - C Q 2-SI-449 2E LPS1 pump A recirc. 2 GL H LO ET 2-SI-450 2E LPSI pump B recire. 2 GL 11 LO ET 2-SI-451 2C LPSI pump B recirc. 2 CK - C Q 2-SI-466 2C SIT test line relief 1.5 REL - C SRV 2-SI-468 2C Shutdown cooling suction relief 1.5 REL - C SRV 2-SI-469 1C Shutdown cooling suction relief 1 REL - C SRV 2-SI-470 2E IPSI pump A suction 6 GA H LO ET 2-SI-614 1E SIT-1 discharge stop 12 GA M0 LO ET Power removed 2-SI-615 2B LPSI header lA injection stop 6 GL MO C Q MT 10 Sec. rJ G ,, O $ w $ w 5 u a z -
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oo H m > < za s2 dx s< 2 Safety Injection 25203-26126, Sh. 3 IC 6 CK - C Q X QP, 2-SI-706A LPSI header IA check QCS IC LPSI header IB check 6 CK C Q X QP, 2-SI-706B QCS LPSI header 2A check 6 CK - C Q X QP, 2-SI-706C IC QCS IC LPSI header 2B check 6 CK - C Q X QP, 2-SI-706D QCS Nj
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-0 RELIEF REQUEST BASIS SYSTEM: SAFETY INJECTION
- 1. Valves: 2-SI-008, 009, 010, 011, 012, 113, 123, 133, 143, 401, 405, 410, 414, 427 Ca teg ory: B Class: 2 Function: Check valves in HPSI flow paths to prevent back flow.
Test Requirement: Exercise valve (full stroke) quarterly. Basis for Relief: Valves cannot be full stroke exercised during reactor operations since the orly full flow path is into the reactor coolant system. HPSI pumps do not have sufficient discharge ressure c (1200 psi) to overcome reactor coolant pressure (2250 psi). Valves cannot be full stroke exercised during cold shutdown since full HPSI flow into the reactor could result in reactor coolant system overpressurization. Alternate Testing: Design flow tests will 'oe conducted during reactor refueling with the reactor head renoved. lhese tests are conducted while filling the reac tor pool cavity and effectively demonstrate that these check valves do operate properly. Partia l stroke exercising will be done quarterly.
- 2. Valves: 2-SI-114, 124, 134, 144, 434, 446 Ca tegory: C Class: 2 Function: Check valves in the LPSI flow paths to prevent backflow.
Te t Requirement: Exercise valve (full stroke) quarterly. Basis for Relief: Valves cannot be full or part stroke exercised during power operation becc.use LPSI pumps cannot overcome SIT pressure downstream of the 2-S1-706 series valves. Pump discharge check valve exercising during operation would require extensive flow path realignment thus rendering the normal LPSI flow path inoperative. Alternate Testing: These check valves are full stroke exercised at cold shutdown during the shutdown cooling mode.
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- 3. Valve: 2-SI-215, 225, 235, 245 Category: C Class: 1 Function: Prevent backflow into safety injection tank.
Test Requirement: Exercise (full stroke) quarterly. Basis for Relief: Valves cannot be full stroke exercised during reactor operation, cold shutdown or refueling since no Gow path exists 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 level and con-sequent plant shutdown, further, if this valve fails to reseat only single valve isolation would exist between the reactor coolant system and the low pressure safety injection tank. Alternate Testing: Valve will be part stroke exercised during cold shutdown.
- 4. Valves: 2-SI-217, 227, 237, 247 Category: C Class: 1 Function: Prevent backflow from RCS to safety injection header.
Test Requirement: Exercise (full stroke) quarterly. Basis for Relief: Valve cannot be full stroke or part stroke exercised dtring reactor operation since the large temperature difference between safety injection system water and the reactor coolant system (approximately 4000F) would cause undue thermal stress of the safety injection nozzles. Alternate Testing: Valve will be full stroke exercised during cold shutdown. 5. INTENTIONALLY LEFT BLANK
?! } l6 SYSTEM: SAFETY INJECTION (Cont'd)
- 6. Valve: 2-SI-652 Ca teg ory: B Class: 1 Function: Isolate shutdown cooling system piping from Reactor Coolant System.
Test Requirement: Exercise and measure stroke time 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 vould require violation of plant interlocks. Alternate Testing: Exercise and measure stroke time during cold shutdown when Reactor Coolant System pressure is less than 300 PSIG.
- 7. Valve: 2-SI-559 Ca tegory: B Class: 2 Function: Isolate minimum flow recirculation piping from refueling water storage tank when Safety Injection System is operating in containment sump recirculation mode.
Test Requirement: Exercise (full stroke) and measure stroke time every three months. Basis for Relief: Valve is required by plant technical specification to be open with valve operator power removed to provide a rr- ' culation flowpath during reactor operation. Alternate Testing: Exercise (full stroke) and measure stroke time during shutdown.
- 8. Valve: 2-SI-660 Category: B Class: 2 Function: Isolate minimum flow recirculation piping from refueling water storage tank when Safety Injection System is operating in containment sump recirculation mode.
Test Requirement: Exercise (full stroke) and measure stroke time every three months. n03 r,2 t) >
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SYSTEti: SAFETY INJECTION (Cont'd) 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. Alternate Testing: Exercise (full stroke) and measure stroke time during cold shutdown.
- 9. Valves: 2-SI-706A, 706B, 706C, 706D Category: C Class: 1 Func tion: Inside containment check valves in the HPSI/LPSI flow pa th.
Test Requirement: Exercise valve (full stroke) quarterly. Basis for Relief: Valves.cannot be full stroked during operation because the only full flow path is into the reactor coolant system. Alternate Testing: Valves will be part stroked quarterly with the HPSI system and will be full stroked at cold shutdown during the shutdown cooling mode. l[b : G w Y w n t
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m d b ds xm SS sx dE xx du s< b x Containment Spray 25203-26126, Sh. 3 2-CS-13A 2C Suction line from RWST 18 GT II LO ET 2-CS-13B 2E Suction line from RWST 18 GT II LO ET 2-CS-13.lA 2B RWST header A stop 18 GA MO O Q X QCS MT 20 Sec. 2-CS-13.lB 2B RWST header B stop 18 GA MO O Q X QCS MT 20 Sec. 2-CS-14A 2C RWST header A check 18 CK - C Q X QP, QR 2-CS-14B 2C RWST header B check 18 CK - C Q X QP, QR 2-CS-15A 2C CTMT sump outlet header A check 24 CK - C Q X QP 2-CS-15B 2C CTMT sump outlet header B check 24 CK - C Q X QP 2-CS-16.lA 2B CTMT sump outlet header A 24 GA M0 C Q MT 30 Sec. 2-CS-16.lB 2B CTMT sump outlet header B 24 GA M0 C Q MT 30 Sec. 2-CS-065 2E CS stop inside containment 8 GA 11 LO ET 2-CS-066 2E CS stop inside containment 8 GA II LO ET RELIEF REQUEST BASIS SYSTE1: CONTAINMENT SPRAY
- 1. Valves: 2-CS-5A, 5B Category: C Class: 2 Func tion: Inside containment check valves in Containment c' pray headers.
Test Requirement: Exercise va' (full stroke) quarterly. Basis for Relief: Valve opera . cannot be verified during reactor operation since the valves are inaccessible during operation. To verify movement of these valves, air must be admitted upstream and valve motion monitored audibly. Water cannot be used for this test since containment wetting would result. Alternate Testing: Valve will be full stroke exercised during extended (greater than three weeks) cold shutdowns and refueling ou tages.
- 2. Valves: 2-CS-13.1A, 13.1B Category: B Class: 2 Function: Refueling Water Storage Tank Outlet Header "A-B" Isolation Valves.
Test Requirement: Exercise valve for operability every three months-Basis for Relief: Failure of this valve in closed position would interrupt an emergency core cooling flow path. Alternate Testing: This valve will be exercised for operability during cold shutdown.
- 3. Valves: 2-CS-14A, 14B Category: C Class: 2 Function: Prevent backflow from Safety Injection Suction Header to the RWST.
Test Regt irement: Exercise valve (full stroke) quarterly. e9Q, g=g c
57 STEM: CONTAINMENT SPRAY (Cont'd) Basis for Relief: Valve cannot be full stroke exercised during reactor operation since the only full flow path is into the reactor coolant system. Valve cannot be full stroked during cold shutdown since overpressurization could result. Alternate Testing: Valve will be part stroke exercised quarterly and full stroke exercised at each refueling.
- 4. Valves: 2-CS-15A, ISB Category: C Class: 2 Function: Prevent backflow into containment sump.
Test Requirment: Exercise to open position quarterly. Basis for Relief: Valve cannct be full stroke exercised without filling containment to design post-accident water depth. Alternate Testing: Valve will be part stroke exercised quarterly. No full stroke exercising is proposed. 2b? } I'h rD
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- 1. Valves: 2-RB-301A,B Catcgory: B Class: 2 Functi,n: Isolate miscellaneous containment heat loads.
Test Requirement: Exercise (full stroke) and measure stroke time quarterly. Basis for Relief: Exercising these valves would result in interrupting cooling water to the reactor coolant pump thermal barriers and oil coolers as well as other loads required during reactor operation. Valve design precludes part stroke exercising. Alternate Testing: Valve will be full stroke exercised on cold shutdown when reactor coolant pumps are not running.
- 2. Valves: 2-RB-37.2A, B Category: B Class: 2 Function: Isolate miscellaneous containment heat loads.
Test Requirement: Exercise (full stroke) and measure stroke time quarterly. Basis for Relief: Exercising these valves would result in interrupting cooling water to the reactor coolant pump thermal barriers and oil coolers as well as other loads required during reactor operation. Valve design precludes part stroke exercising. Alternate Testing: Valve will be full stroke exercised on cold shutdovin when reactor coolant pumps are not running. 5
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i<ELIEF REQUEST BASIS SYSTEM: MAIN STEAM
- 1. Valve: 2-MS-64A Category: B-C Class: 2 Function: Stop flow from steam generator No.1 following steam line rupture downstream of valve.
Test Requirement: Exercise valve for operability and measure stroke time every three months. Basis for Relief: Full stroke testing of this valve would require plant shu tdown. Alternate Testing: Part-stroke exercise every three months and full stroke exercise and measure stroke during cold shutdown.
- 2. Valve: 2-MS-64B Ca tegory: B-C Class: 2 Function: Stop flow from steam generator No. 2 following steam line rupture downstream of valve.
Test Requirement: Exercise valve for operability and measure stroke time every three months. Basis for Relief: Full stroke testing of this valve would require plant shutdown. Alternate Testing: Part-stroke exercise every three months and full stroke exercise and measure st-oke time during cold shutdown.
- 3. Valve: 2-MS-65A
' tegory:
B 1s: 2 Function: Startup bypass valve around main steam isolation valve for No. 1 steam generator. Test Requirement: Exercise valve (full stroke) for operability and stroke time every three months.
- 20) )
SYSTEM: MAIN STEAM (Cont'd) Basis for Relief: Valve is nomally closed and not required to change position during plant operation. Failure of this valve in the open position during exercise would jeopardize the ability to stop steam flow in the event of downstream rupture. Alternate Testing: Full stroke exercise and measure stroke time during cold shutdown.
- 4. Valve: 2-MS-65B Category: B Class: 2 Function: Start-up bypass valve around main steam isolation valve for No. 2 steam generator.
Test ReqJirement: Ev.ercise valve (full stroke) for operability and stroke time every three months. Basis for Relief: Valve is normally closed and not required to change position during plant operation. Failure of this valve in the open position during exercise would jeopardize the ability to stop steam flow in the event of a down-stream rupture. Alternate Testing: Full stroke exercise and measure stroke time during cold shutdown.
- 5. Valve: 2-MS-190A Category: B Class: 2 Func tion: Provide control of steam flow from No. 1 steam generator to atmosphere during cooldown.
Test Requirement: Exercise (full stroke) for operability and measure stroke time every three months. Basis for Relief: Operation of valve during plant operation could result in steam flow transient. Isolation of this valve to allow exercising during operation could reduce plant ability to withstand r. turbine trip transient. Alternate Testing: Full stroke exercise and measure stroke time during cold shutdown.
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SYSTEft: MflN STEAM (Cont'd)
- 6. Valve: 2-MS-190B Category: B Class: 2 Func tion: Provide control of steam flow from No. 2 steam generator to atmosphere during cooldown.
Test Requirement: Exercise (full stroke) for operability and measure stroke time every three months. Basis for Relief: Operation of valve during plant operation could result in steam flow transient. Isolation of this valve to allow exercising during operation could reduce plant ability to withstand a turbine trip transient. Alternate Testing: Full stroke exercise and measure stroke time during cold shutdown. 2 ; , n m m H w
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?T X FTCS LT X LLRT 2-Clf-198 2A RC pump seals controlled leakoff .75 GL A0 0 Q X QCS No RCP's in operation MT 5 Sec.
FT X FTCS LT X LLRT 2-Cil-505 2A RC pump seals controlled leakoff .75 GL A0 0 Q X QCS No RCP's in operation MT 5 Sec. FT X FTCS LT X LLRT 2-CH-506 2A RC pump seals controlled leakoff .75 GL A0 0 Q X QCS No RCP's in operation MT 5 Sec. FT X FTCS LT X LLRT PI 2-CH-516 2A Letdown to purification demin. 3 GL A0 0 Q X QCS MT 5 Sec. FT X FTCS LT X LLRT PI 2-CS-4.1A 2A Containment spray 8 GA M0 C Q MT 15 Sec. LT X LLRT G m w a m
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x - s - a w s e< m x5 SO~ " w D dC 3 $3 $ 55 s E9 WW N H S B ra MB 38 us n GE d5 @ s W 82 Hs ad N :s M Containment Isolation 2-CS-4 lB 2A Containment spray 8 GA M0 C Q MT 15 Sec. LT X LLRT 2-SI-312 2A Nitrogen supply to SI tanks .75 GL A0 0 Q MT 5 Sec. FT LT X LLRT 2-SI-463 2AE SI tank test line 2 UA 11 LC ET LT X LLRT 2-SI-709 2AE Shutdown cooling isolation 12 GA H LC ET LT X LLRT 2-MS-191A 2A Steam gen. blowdown sample .5 GL A0 0 Q MT 5 Sec. FT LT X LLRT 2-MS-191B 2A Steam gen. blowdown sample .5 GL A0 0 Q MT 5 Sec. FT LT X LLRT 2-MS-220A 2A Steam gen. bottom blowdown 2 GL A0 0 Q MT 5 Sec. FT LT X LLRT
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FT X FTCS PI LT X LLRT 2-RW-21 2AE Refueling water purification 4 GA II LC ET LT X LLRT 2-RW-63 2AE Refueling water purification 4 GA II LC ET LT X LLRT 2-RW-154 7AE Refueling water purification 4 GA II LC ET LT X LLRT 2-RW-132 2AE Refueling & 'er purification
. 4 GA II LC ET LT X LLRT 2-SSP-16.1 2A "TMT sump to aerated drain tk. 3 GL A0 C Q MT 5 Sec.
FT X FTCS PI LT X LLRT 2-SSP-16.2 2A t.TMT sump to aerated drain tk. 3 GL A0 C Q MT 5 Sec. FT N,n LT X LLRT L
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FT LT X LLRT 2-AC-15 2A Containment air sample 1.5 BFLY A0 0 Q MT 5 Sec. FT LT X LLRT
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- 1. Valve: 2-C H-08 9 Ca tegory: A Class: 2 Function: Provide containment isolation for RCS letdown piping on containment isolation signal.
Test Requirenent: Exercise (full stroke) and measure stroke time every three months. Basis for Relief: Operation of this valve during plant operation would cause undesirable thermal transients on the regenerative heat exchanger. This canponent has a limited number of design thermal transients. Alternate Testing: Exercise (full stroke) and measure stroke time during cold shutdowns.
- 2. Valve: 2-CH-198, 505, 506 Category: A Class: 2 Function: Isolate Reactor toolant pump seal leakoff line at containment penetration.
Test Requirement: Exercisc and measure stroke time every three months. Basis for Relief: These valves are required to be open anytime the reactor coolant pumps are operating. Alternate Testing: Exercise and measure stroke time during cold shutdown ' when reactor coolant pumps are secured.
- 3. Valve: 2-CH-516 Category: A Class: 2 Function: Isolate Reactor Ccolant System letdown line on contain-ment isolation signal.
Test Requireme.it: Exercise (full stroke) and measure stroke time every three months. nQ3
- f. U / i ,'i.. (
SYSTEM: CONTAINMENT ISOLATION (Cont'd) Basis for Relief: Operation of this valve during plant operation would cause undesirable thermal transients on the regenerative heat exchanger. This component has a limited number of design thermal transients. Alternate Testing: Exercise (full stroke) and measure stroke time during cold shutdown.
- 4. Valves: See List of Containment Isolation Valves Ca tegory: A, AE Class: 2 Function: To insure containment integrity in event of requirements to isolate.
Test Requirement: Exercise all active valves quarterly and determine leak tightness not less than once every two years. Basis for Relief: This list consists of valves whose only safety function is containment isolation. These valves are and have been leak tested under Tech. Spec. requirements using Appendix J to 10CFR50, Type C tests. See MP2 Tech. Spec's. 3.6.1.2. Alternate Testing: In that CIV leakage tests are conducted in accordance with primary containment integrity tests, the individual valve leakage rate analysis required by IWV-3420 (f) is not done. Leakage rates of individual valves are recorded and canbined to arrive at an integrated leak rate, which is then compared to the allowable combined leakage rate for all penetrations and valves subject to Type B and C tests. Millstone Unit No. 2, therefore, requests a waiver from IWV-3420 (f) for contaimnent isolation valves and propo_es the LLRT leakage criteria as an alternate. NNECO also requests a waiver from the require-ments of IWV-3420 (g). We propose to continue to demonstrate permissible leakage rates by complying with the requirements of local and integrated leak rate test criteria as included in Millstone Unit No. 2 Technical
?pecifications.
0O j} tf-SYSTEti: C0ilTAlfMEt4T ISOLATI0t1 (Cont'd)
- 5. Valve: 2-SI-651 Category: A Cla ss: 1 Function: Isolate shutdown cooling system piping from Reactor Coolant System.
Test Requirement: Exercise and measure stroke time every three months. Basis *or Relief: Valves are locked closed when Reactor Coolant System pressure exceeds 300 PSIG to protect the low pressure shutdown piping. Valve exercise would require violation of plant interlocks. Alternate Testing: Exercise and measure stroke time during cold shutdown when Reactor Coolant System pressure is less than 300 PSIG.
- 6. Valves: 2-AC-4,5,6,7 Category: A Class: 1 Function: Containment purge isolation.
Test Requirement: Exercise (full stroke) and measure stroke time quarterly. Basis for Relief: Thase valves are passive during reactor operation. They are tagged shut and electrically disabled. Opening this valve could jeopardize post-accident containment integrity since closure during post-LOCA blowdown can-not be assured. Alternate Testing: Exercise (full stroke) and measure stroke time during cold shutdown when containment airborne radioactivity levels are within discharge specification.
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~ - LEGEND FOR VALVE TESTING Q - Exercise valve full stroke for operability every three (3) months. QP - Exercise valve part stroke for operability every three (3) months. QCS - Exercise valve full stroke for operability during cold shutdowns. QPCS - Exercise valve part stroke for operability during cold shutdowns. QR - Exercise valve full stroke for operability during refueling. QPR - Exercise valve part stroke for operability during refueling. f1T - Take stroke time measurements and compare to the stroke time limiting value per Section XI Article IWV-3410. PI - Visually observe, during refueling, actual valve position to confirm that remote valve position indicat ons accurately reflect valve operation. FT - Remove actuator power from valves with fail-safe actuators to confirm that the valve travels to its fail-safe position every three (3) months. ET - Verify and record valve position before operations are performed and af ter operations are completed, and verify that the valve is locked or sealed. LT - Leak test valve per Section XI Article IWV-3420. LLRT - Leak test valve in conformance with the criteria specified in Appendix "J" of 10 CFR 50. SRV - Test safety and relief valves per Section XI Article IWV-3510. FTCS - Remove actuator power from valves with fail-safe actuators to confirm that the valve travels to its fail-safe postion during cold shutdowns. 7
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13 Q TABLE IWV - 2 SAFETY / RELIEF VALVE SETPOINTS Service Valve No. Type Setpoint (Tol.) Safety Injection Tanks 2-SI-007 1" Rel 250 2-SI-211 1" Rel 250 2-SI-221 1" Rel 250 2-SI-231 1" Rel 250 2-SI-241 1" Rel 250 HPSI Header B Relief 2-SI-409 .75 Rel 1750 HPSI Header A Relief 2-SI-417 1" Re1 2735 LPSI Header Relief 2-SI-439 .75 Rel 500 SIT Test Line Relief 2-SI-466 1.5 Rel 500 Shutdown Cooling Suction Relief 2-SI-468 1.5 Rel 300 Shutdown Cooling Suction Relief 2-SI-469 1" Rel 300 Pressurizer Relief 2-RC-200 2.5 RV 2500 (s1%) Pressurizer Relief 2-RC-201 2.5 RV 2500([1%) Pressurizer POR Valves 2-RC-402 2" Gate 450 (sol. op.) Pressuri7er PORC Valves 2-RC-404 2" Gate 450 (sol. op.) Chanjing Pump A Relief 2-CH-326 .75 Rel 2735 Charging Pump B Relief 2-CH-325 .75 Rel 2735 Charging Pump C Relief 2-LH-324 .75 Rel 2735 Main Steam Header 3 Relief 2-M S-239 6" Rel 1050 (+1%) 2-M S-240 6" Rel 1045 (+1%) 2-MS-241 6" Rel 1025 (+1%) 2-MS-242 6" Rel 1005 (+1%) 2-MS-243 6" Rel 1050 (+1%) 2-M S-244 6" Rel 1035 (+1%) 2-MS-245 6" Rel 1015 (+1%) 2-MS-246 6" Rel 1000 (+1%) Main Steam Header A Relief 2-MS-247 6" Rel 1000 (+1%) 2-MS-248 6" Rel 1050 (+1%) 2-MS-249 6" Rel 1015 (+1%) 2-MS-250 6" Rel 1045 (+1%) 2-MS-251 6" Rel 1035 (+1%) 2-MS-252 6" Rel 1025 (+1%) 2-MS-253 6" Rel 1050 (+1%) 2-MS-254 6" Rel 1005 (+1%)
- 20) l.
SYSTEM PRESSURE TESTS Ar t ic le s IWA-5000, IWB-5000, IWC-5000 and IWD-5000 discuss the requirements of system pressure tests for Classes 1, 2 and 3 components. Table BCD-5000 presents the system pressure test requirements for the Millstone Unit 2 components and notes departures from Code where it was deemed necessary. Test requirements for open-ended lines such as suction lines from storage tanks, and which receive static tests, are not addressed in the table. The location of check valves in several systems that penetrate the primary containment preclude the Class 1 pressure test boundary from extending out-ward beyond the first of such valves, usually located inside containment even though the Class change boundary is outside containment. In these cases, the Class I leakage and pressure test boundary voitld be the inside check valve. Conversely, pressure tests of Class 2 systems, which are out-s id e c on ta inmen t , would have to be bounded at a stop valve which may or may not be the Class 1/ Class 2 boundcry. Precautions must be taken in view of the dif ferences that exist in Class 1/ Class 2 test pressures to prevent overpressurization of the Class I components. As an alternate to the Summer, 1975 Addendum, NNECO proposes to utilize the rules of the Winter, 1977 Addendum, IWA-5213, to define test condition holding time for all pressure tests. In systems which contain pumps, it will not be possible to utilize the pump casing as the boundary between high pressure and low pressure tests without overpressurizing suction piping during the high pressure test. In these cases, the discharge isolation valve will be considered the test boundary.
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. TABLE BCD - 5000 SYSTDI PRESSURE TESTS TEST CODE TEST SYSTDI PRESSURE PRESSURE RDIARKS (psig) (p sig)
Class 1 (IWB-5000) Reactor Coolant Pressure Boundary System Leakage Test 2250 2250 In Compliance with Cod e System Hydrostatic Test 2430 0 2430 0 In Compliance with 200F 200F Code Class 2 (IWC-5000) l! PSI 1125 1125 In Complicnce with Code (IWC-5220c ) Containment Spray 254 254 In Compliance with Cod e (IWC-5220c) LPSI/ Shutdown Cooling Pump suction piping from 375 375 In Compliance with 2-SI-651 to 2-SI-432 and Code 2-SI-444. Pump discharge piping 625 625 In Compliance with Code Bla in S team 1250 1250 In Compliance with from SG's to 2-MS-04A/B Cod e 2-BIS-65A/B, and 2-MS-201 and 2-!!S-202 Feedwater f rom 2-FW-5A/B and 1250 1250 In Compliance with 2-FW-12A/B to SG 's Cod e CV CS Boric Acid subsystem 188 188 In Compliance with Code Char);ing pump suction 188 188 In Compliance with header Code
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[ (I , 9 v - MILLSTONE UNIT NO. 2 SYSTDI PRESSURE TESTS (cont'd) TEST CODE TEST SY STDI PRESSURE PRESSURE RDIARKS (psig) (psig) Charging pump discharge 3419 3419 In Compliance with header Code Letdown f rom RCS, Valve 3106 3106 In Compliance with 2-CH-516 to RHX to Code 2-CH-89 Class 3 (IkD-5000) Spent Fuel Pool Cooling Pump Suction piping 55 55 In Compliance with Code Pump Discharge piping 110 110 In Compliance with Code Auxiliary Feedwater Aux. Feedpump suction 55 55 In Compliance with p iping Code Aux. Feedpump discharge 1760 1760 In Compliance with piping to 2-FW-43 A/B Code Aux. Feedpump discharge 1210 1210 In Compliance with piping from 2-FW-43A/B Code to 2-FW-12A/B RBCCW 165 165 In Compliance with Code Service Wa ter Cast Iron underground 94 94 In Compliance with Code Relief Valve inlet piping 188 94 See Note 1 Remaining system piping 110 94 See Note 1 Chilled Water 55 55 In Compliance with Code Main Steam f rom valves 2-MS-201 and 1100 1100 In Compliance with 2-MS-202 to SG Aux. Feedpump Code Tu rb ine
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n - NOTES
- 1. The service water system consists of piping and components designed to three different pressures, depending upon service conditions and material selection:
Cast Iron Underground PD= 85 psig Relief Valve Inlets PD = 150 psig Balance (majority) of System PD = 100 psig In most instances, it is not possible to isolate these sections from each other to permit Code pressure tests. NNECO requests a waiver from the requirements of IWD-5200 (a) for the service water system for the two higher pressure sections, and as an alternate, propose to test the entire service water system to 94 psig, test pressure, based on the underground portion. Although this pressure is lower than the design pressure for most of the service water system, it is approximately 1 times the system operatirg pressure and would constitute a meaningful hydrostatic test. 90.; .- LU i j,' _4
n .. DOCKET NO. 50-336 ATTACIfMENT 2 MILLSTONE NUCLEAR POWER STATION, UNIT No. 2 RESPONSES TO REFERENCE (3), ISI PROGRAM m, JUNE, 1979 LJ k uy 12 1
w . PAGE I-2
- 1. Use of Appendix III of Section XI,1974 edition through Winter,1975 is acceptable, however, the recording of indications should be as follows:
Record all indications which produce a response of 50% or greater of primary reference level . Evaluate all indications producing a response of 100% or greater of primary reference level .
Response
Indications which produce a response of 50% or greater of primary reference level will be recorded. Indications which p 'oduce a response of 1001 or greater of primary reference level will be evaluated.
- 2. Use of technical specifications for examination of hydraulic snubbers is acceptable if technical specification procedures meet or exceed code requirements. Please ,rovide documentation that shows the extent of technical specification examindtion requirements.
Response
ASME Section XI, Category B-K-2 requires a visual examination of each support at least once per inspection interval which includes verifying the snubber setting. Tech. Spec. 4.7.8.1 on hydraulic snubbers requires a visual examination of each snubber every 18 months plus a representative sample of at least 10 snubbers (Class 1, 2, and 3) to be selected and functionally tested to verify correct movement during the same time period. Inasmuch as Appendix A to DPR-65 is a document issued by the NRC, it would appear that you would have direct access to this information. PAGE I-3 Class 1 Components
- 1. Can nozzle to vessel welds N-2, N-4, and N-6 be examined using surface methods?
Response
Nozzle to vessel shell welds N-2, N-4, and N-6 are inaccessible on the lower
half for the reasons discussed in the January 25, 1979 su bni t tal . The access constraints which limit the volumetric examination of these welds also preclude surface examination as both would be conducted from outside the vessel. Vessel support pads, clearance between the vessel and bio-shield and permanently installed insulation prevent access to this area. NNECO will continue to study methods to conduct remote examinations of these areas, as previously stated. PAGE I-10
- 1. Concerning your request for relief from examination of vessel cladding, will examination of the closure head welds also provide meaningful inforuation about the condition of the cladding?
Response
We do not consider that the Category B-B examinations, conducted at or near the end of the inspection interval, would be meaningful in regard to determining the surface condition of cladding, per Category B-I. Appendix I, Paragraph I-6310 (b) cautions ultrasonic operators on interpreting reflectors from certain metallurgical discontinuities and geometric conditions. During refueling out-ages, the condition of accessible cladding on the vessel surfaces is visually observed. NNECO considers these examinations to be more meaningful, and more frequent, than determinations from the outside surfaces during Categcry B-B inspections. In addition, a more complete evaluation will be made in con-junction with the B-N-3 examinations, per our January 25th submittal.
- 2. In Note 10, you state that safety injection valve bonnet bolting has spherical ends, thus precluding volumetric examination. Since the probable point of crac < initiation and growth is the thread root area, has an ultrasonic exam-ination technique utilizing response from thread roots been considered? If this alternate volumetric examination is not possible, is a surf ace examination of these volts possible?
Re s pon s_e_ There are eight valves in the safety injection system, all 12" swing checks performing similar functions and containing 16 2" studs each. :_sion rules in effect at the time of valve procurement provided for surface examinat.an of the studs. Because of the spherical end problem noted in the previous submittal, NNECO proposes to perform a visual inspection, per the requirements of examin-a tion Category B-G-2. A surface examination would not be practical because of the difficulty in removing these studs from the valve bodies. A visual in-spection of these studs is compatible with examination Category B-G-2 in the Summer,1978 Addenda, in that only bolting larger than 2" requires a volumetric or surface examination.
5 ' k CLASS 2 COMPONENT S
- 1. Examination of hydraulic snubbers to requirements of technical specifications is acceptable only if technical specifications meet or exceed code requirements.
Please compare and state the differences.
Response
ASME Section XI, Category C-E-2, requires a visual examination of all non-exempt snubbers during the inspection interval. Tech. Specs. 4.7.8.1 require a visua l examination of all snubbers every 18 months plus a functional test of at least ten snubbers (Class 1, 2 and 3) every 18 months.
- 2. Note 2, Page II-6, states that volumetric examination of the shutdown heat ex-changers is precluded due to weld design. Please provide details of the nozzle-to-vessel welds that explain why no volumetric examination can be done.
Response
The two shutdown heat exchangers were manufactured to the requirements of ASME Section III for Class C vessels. Although welding in the vessel seams was radiogrcphed, the channel nozzles were inspected using surface methods, per rules that were in effect at the time of manufacture. Although it may be possible to perform limited volumetric examination, we do not believe that the results would justify the potential expense, as is the case in most instances where the weld joint was not designed to accommodate radiographic or ultrasonic examination. These components are only operated to support cold shutdowns, or containment sump recirculation in an emergency mode, and the nozzles are not subjected to high stresses under any mode of operation. NNECO therefore pro-posed a surface examination of each nozzle as being the most meaningful inspection for assurance of structural integrity for the shutdown heat exchangers. I b :}}