View source for A07351, Forwards Response to NRC Questions Re Util Inservice Testing Program & Updated Version of Pump Table.Background Data Supporting Svc Water Pump Vibration Limits Proposed in Relief Request Also Encl

{{Adams
| number = ML20153D480
| issue date = 08/26/1988
| title = Forwards Response to NRC Questions Re Util Inservice Testing Program & Updated Version of Pump Table.Background Data Supporting Svc Water Pump Vibration Limits Proposed in Relief Request Also Encl
| author name = Mroczka E
| author affiliation = NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES
| addressee name = 
| addressee affiliation = NRC OFFICE OF ADMINISTRATION &amp; RESOURCES MANAGEMENT (ARM)
| docket = 05000336
| license number = 
| contact person = 
| document report number = A07351, A7351, NUDOCS 8809020221
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE, UTILITY TO NRC
| page count = 66
| project = 
| stage = Request
}}

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NORTHEAST UTILITIES                                     o.ner.i Ome.. . som.n sir..i. B.rnn. Conn.ciicui l             e        NaNU*~                                    P.O. BOX 270
                 ***''**'***"***                                      HARTFORD CONNECTICUT 06141-0270 L     L   J [',((C"%,",[                                         (203) 665-5000 August 26, 1988 Docket No. 50-336 A07351 Re:     10CFR50.55a(g)
U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C.       20555 Gentlemen:
Hillstone Nuclear Power Station, Unit No. 2 Inservice Testina Proaram (TAC #59265)
By {{letter dated|date=June 27, 1985|text=letter dated June 27, 1985}},(I) Northeast Nuclear Energy Company (NNECO) submitted, as required by 10CFR50.55a(g), a description of the Inservice Testing (IST) Program and "requests for relief" from ASHE code requirements as necessary for the second ten-year inspection interval for Hillstone Unit No. 2.
By {{letter dated|date=July 29, 1986|text=letter dated July 29, 1986}},(2) the NRC Staff requested that NNECO provide additional information regarding the IST Program NNEC0 responded to the request by letter dated December       at Hillstone      Un{t 3) No.That 23, 1986.               2.
submittal included an updated version of the IST Program, revised "requests for relief," and the additional information requested by the Staff.
In response                                       for additional information dated May 27,1987,g the NRC Staff's requestNNEC0 provided information regarding the IS (1)    J. F. Opeka letter to the Director of Nuclear Reactor Regulation, dated June 27,1985, "Hillstone Nuclear Power Station, Unit No. 2,                     Inservice Inspection and Testing Program."
(2)    D. H. Jaffe letter to J. F. Opeka, dated July 29, 1986, "Hillstone Unit No. 2 Request for Additional Information."
(3)    E. J. Hroczka letter to the Director of Nuclear Reactor Regulation, dated December 23, 1986, "Hillstone Nuclear Power Station, Unit No. 2 Inservice Inspection and Testing Program, Request for Additional Information."
(4)    D. H. Jaffe letter to E. J. Hroczka, dated May 27, 1987, "Hillstone Nuclear Station, Unit No. 2 (TAC #59265)."
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i U.S. Nuclear Regulatory Commission A07351/Page 2 August 26, 1988 by {{letter dated|date=July 31, 1987|text=letter dated July 31, 1987}},(5) which NNECO believed to fully address the Staff's request.
As a result of NRC Staff questions of June 2,1987, and a meeting between NRC Staff letter personnel  and30, dated October  NNECO 1987, on gust 25 and 26,1987, NNEC0 submitted, in a a revised IWP (Pump) and IWV (Valve) Testing Program for the second ten-year inspection interval for Millstone Unit No. 2.
This submittal superseded and replaced all previous submittals made by NNEC0 related to pump and valve testing for the second inspection interval, and was believed to be a complete, comprehensive package. In addition, all relief requests were revised, updated, and renumbered. Also included was an updated program for Emergency Diesel Generator Auxiliary Systems Testing and an item-by-item discussion of questions and concerns raised at the August 25 and 26, 1987 meeting between the NRC Staff and NNECO.
By {{letter dated|date=June 28, 1988|text=letter dated June 28, 1988}},(7) the NRC Staff requested additional informa-tion regarding our Inservice Testing Program and requested that NNEC0 respond within 60 days of receipt of the letter. NNECO hereby submits the response to the NRC questions as Attachment 1. Attachment 2 is an updated version of the pump table (Table IWP) as requested in Question No. 1 in Attachment             1.
Attachment 3 provides the background data supporting the Service Water Pump vibration limits proposed in Relief Request RR-IWP-1. Attachments 4 through 13 provide revised Relief Request in support of NNEC0's responses included in Attachment 1. The revised listing of safety-related instrument air accumula-tors, as requested in Question No. 18 in Attachment           1, is provided as Attachment 14. Attachment 15 provides various corrected valve list pages as requested in Question No. 17 in Attachment 1. Attachment 16 is a set of the revised Class 2 isometric drawings for the Hillstone Unit No. 2 second ten year program.
(5)   E. J. Mroczka letter to       U.S. Nuclear Regulatory Commission, dated July 31,1987, "Hillstone Nuclear Power Station, Unit No. 2, Inservice Inspection and Testing Program."
(C)   E. J. Mroczka letter to       U.S. Nuclear Regulatory Commission, dated October 30, 1987, "Hillstone Nuclear Power Station, Unit No. 2, Inservice Inspection Testing Program."
(7)   D. H. Jaffe letter to E. J. Mroczka, dated June 28, 1988, "Millstone Nuclear Power Station, Unit No. 2 Inservice Testing" (TAC No., 59265).
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U.S. Nuclear Regulatory Commission A07351/Page 3 August 26, 1988 NNECO trusts that this submittal adequately resolves all existing Staff concerns. We have imple     ted the program previously approved by the NRC Staff on January 3,1986,        and will continue to follow this program pending review and approval of the changes set forth herein.
Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY E.yr'oczka f d'      W Senior Vice President Attachments cc:   W. T. Russell, Region I Administrator D. H. Jaffe, NRC Project Manager, Hillstone Unit No. 2 W. J. Raymond, Senior Resident Inspector, Hillstone Unit Nos. 1, 2 and 3 i
(8)   A. C. Thadani letter to J. F. Opoka, dated January 3,1986, "Millstone Unit No. 2 - Inservice Inspection and Testing Program - Second 10 year Interval . "

Docket No. 50 336 A07351 Attachment 1 Additional Information on Inservice Testing August 1988

ATTACHMENT 1 Page 1 of 8 RESPONSE TO NRC REQUEST FOR ADDITIONAL INFORMATION MILLSTONE UNIT 2 PUMP AND VALVE INSERVICE TEST PROGRAM 10  Pump table (Table IWP parameters are being m)easured:does not indicate that the following pump Pumos                     Parameter Auxiliary Feedwater Pumps                    Flow H.P. Safety Infection Pumps                  Flow L.P. Safety In:lection Pumps                 Flow Containment Spray Pumps                      Flow         .
Charging Pumps                              Differential Pressure Boric Acid Pumps                             Flow These parameters must be measured as re@ ired unless relief is requested and approved. This licensee indicated in their response to question II.3 during the IST working meeting held August 26 and 27, 1987 that these pump parameters are being measured.           The licensee,also agreed during that meeting to include additional information in the pump listing table. Table IWP should be corrected to show the actual testing performed and any required relief requests should be provided.
RESPONSE - An outdated version of the pump table (Table IWP) was inadvertently included with the submitted program.         It was the intent to show these parameters as being measured. The correct table is included as Attachment 2.
20  Pump relief request RR-IWP-1 is a new relief request that has not been previously reviewed. IWP-3210 states that if the allowable ranges of Tablo IWP-3100-2 cannot be met, the owner shall specity in the record of tests the reduced range limits to allow the pump to fulfill its function, and those limits shall be used in lieu of the ranges given in the Code. Relief request RR-IWP-1 provided an adequato discussion for not mooting the maximum vibratkon velocity limits for the service water pumps, however, doubling the OM-6 limits may not be justified based on the historical test data for the service water pumps. Provide the test data and/or other information that demonstrates that proposed limits are justified and will not permit continued operation with a seriously degraded i      Pump.
RESPONSE - Attachment 3 provides the background data supporting the service water pump vibration limits proposed in Rolief Roquest RR-IWP-1. This information shows that the proposed vibration limits are equivalent, for those pumps to those proposed by OM-6 for "standard" pumps. Recogniz1ng that those levels are higher than normal and, under some unlikely conditions, not fully indicative of pump / motor conditions, Relief Roquest RR-IWP-1 has been revised to include additional actions, beyond those required by the applicable i
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ATTACHMENT 1 Page 2 of 8 ASME codes and OM-6, which will be implemented when these pumps are in the Alert Range and is shown in Attachment 4.
These additional actions will provide additional assurance that the pump will not be operated in a seriously degraded condition and will be fully capable of fulfilling its safety related function.
: 3. The code requires that check valves be exercised to their safety function position (s) to verify that they can go to that position (s) if required to mitigate the conse@ences of an accident, take the plant to the safe shutdown condition, or to maintain the plant in the safe shutdown condition. It is the NRC staff position that l'.stening for an audible sound is not a valid method of verifying a valve in the fully open position since the sound could result from any mechanical contact inside the valve body and does not necessarily indicate that the disk has contacted the stop. Valvos 2-CS-5A and 5B (Relief Request RR-IWV-3) are never verified to full-stroke exercise open. This was left open for the licensee to resolve as discussed in item D.1 of the IST working meeting held August 26 and 27, 1987. The full-stroke capability of these valves must be verified by some positive means such as valvo disassembly, inspection and manual exercising.
RESPONSE - As stated in Relief Request RR-IWV-3, and in response to Item D.1 of the IST working meeting held August 26 and 27, 1987, Northeast Nuclear Energy Company considers an air test which demonstrates full, free ' movement of the valve disk substantially more effective in demonstrating actual operability than disassembly of a valve. These valves are not subject to wear since no normal plant operations cause flow in this pipe. These valves are not sucject to corrosion since this pipe is normally dry. The proposed test adequately demonstratos that these valves open on demand.
Northeast Nuclear Energy Company considers that frequent disassembly, inspection and manual operation of those valves as required by the NRC staff will present more of a hazard to continued reliable operation than the testing originally proposed in Relief Request RR-IWV-3.
However, in view of the NRC Staff's continued refusal to accept the Northeast Nuclear Energy Company proposed alternativo testing and the repeated statomont of the NRC Staff position that "... when valvo disassembly is used to at least verify thefrom ono valvo  full-stroke  capability each group  of identical            of check  valves,imilar valves in s applications should bo disassembled, inspected, and manually exorcised each refueling outago.", Relief Roquest RR-IWV-3 han boon revised to require disassembly, ins manual oxorcise of one valvo each refueling.pection              Acceptance  and of the NRC mandated testing is based on the relatively low radiation levels and ready physical access to those valves.
The revised Relief Roquest is provided as Attachment 5.
: 4. Rollef Roquest RR-IWV-4 does not provido sufficient detail in the

ATTACHMENT 1 Page 3 of 8 basis for relief. The basis for relief should explain why flow
!      cannot be established through valves 2-CS-14A and 14B into the RCS durinfishedintothecontainment.
estab                          power operation   and why Also,     howcontainment spray cannot is it verified    thatbe valves 2-CS-14A and 14B are full-stroke exercised during testing at refueling outages.
RESPONSE - The batis for relief has been revised to indicate that the safety injection pumps are not able to overcome the pressure of the Reactor Coolant System during operation and to show that no other flow path would be capable of accepting full design flow. These valves will be full stroke tested during refueling by passing full design flow through the valves while filling the refueling pool. The revised relief request is included as Attachment 6.
: 5. Relief Request RR-IWV-5 idantifies a sample disassembly and inspection intarval of one valvo every 40 months for valves 2-CS-15A and ISB. The NRC staff position is that when valve disassembly is used to verify the full stroke capability of check valves, at least one valve from each group of identical valves in similar applications should be disassembled, inspected and manually exercised each refueling outage.           This was left open for the licensee to resolve as discused in Item D.3 of the IST working meeting held August 26 and 27, 1987.
RESPONSE - As identified in Relief Request RR-IWV-5, and in response to Item D.3 of the IST working meeting held August 26 and 27, 1981, Northeast Nuclear Energy Company considers the more frepant disassembly and inspection of these valves to have a higher potential for adverse impact than the proposed examination schedule. These valves normally sit in a high purity boric acid solution. Examinations conducted during the previous thirteen years of operation have identified no degradation in these valves. The valves operate only in the event of an accident and are thus not subject to significant wear between refueling outages.                In addition, more frequent examination increases personnel exposure to looso radioactivo materials increases personnel radiation exposure, and increases gene, ration of both liquid and solid radioactive waste.
Northeast Nuclear Energy Company requests the NRC reconsidor                ,.
the frequency of disassembly, inspection and exorcise required to assure operability of those valves and approve the proposed and   oxorciseonce-por-forty-months as adoquate to assure      disassembly,ity the operabilof theinspection, valvos.
: 6. Rolief Roquest RR-IWV-8 identifico a sample disassembly and inspection interval of one valve overy 40 months for valves 2-SI-215, 225, 235 and 245. The NRC Staff position is that when valvo disassembly la used to verify the full stroko capability of check valves, at least ono valve from each group of identical
                                                     ,-  s-                    --

ATTACHMENT 1 Page 4 of 8 valves in similar applications should be disassembled, inspected and manually exercised each refueling outage. These valves were discussed in Item E.1 of the IST working meeting held August 26 and 27, 1987.
RESPONSE - As indicated in Relief Request RR-IWV-8, high flow testing which, while less than full design flow will be sufficient to fully open the valve and should identify significant maloperation of the valve, would be performed each refueling outage in addition to the proposed disassembly of one valve every 40 months. Northeast Nuclear Energy Company considers the more frequent disassembly and inspection of these valves proposed by the NRC Staff to have a highcr potential for adverse impact than the examination schedule proposed in Relief Requent RR-IWV-8. These valves normally sit in a high purity boric acid solution. Examinations conducted during the previous thirteen years of operation have identified no degradation in these valves. The valves operate only infrequently and are thun not subject to significant wear between refueling outages. In additten.
more fropont examination increases personnel exposure co loose radioactive materials increases personnel radiation exposure, increases generatkon of radioactive waste, and could extend the duration of planned refueling shutdowns and result in significant added costs. Northeast Nuclear Energy Company considers the proposed testing fully adequate to assure the operability of this valve.
Northeast Nuclear Energy Company will continue to explore means to verify, physically, that the valvo disk moves to the fully open position under the available test flow conditions. If a practical means of verifying valve disk position can be developed and the available t mt flow is sufficient to fully open the valve Northeast Yclear Enargy Company will full stroke test each valve eact refueling.
However, Northeast Nuclear Energy Company requests the NRC reconsider the frequency of disassembly, inspection and exercise required to assure operability of these valves and approve the combination of a high flow test each refueling and a once-per-forty-months disassembly, inspection, and exercise. Relief Request RR-IWV-8 has been revised to reflect this alternative testing and is included as Attacnment 7.
: 7. Relief Request RR-IWV-9 identifies a sample dinassembly and inspection interval of one valve every 40 months for valves 2-SI-217, 227, 237    and 247. The NRC Staff position is that when valve disassembly 1s used to verify the full stroke capability of check valves, at least one valve from each group of identical valves in similar applications should be disassembled, inspected and manually exercised each refueling outage. These valves were discussed in Item E.1 of the IST working meeting held August 26 and 27, 1987.

ATTACHMENT 1 Page 5 of 8 RESPONSE - As indicated in Relief Request RR-IWV-8 and 9, high flow testing which, while less than full design flow will be sufficient to fully open the valve and should identify significant maloperation of the valve would be performed each refueling outage in addition to the proposed disassembly of one valve every 40 months. Northeast Nuclear Energy Company considers the more frequent disassembly and inspection of these valves to stave a higher potential for adverse impact than the proposed examination schedule.
These valves normally sit in a high purity boric acid solution. Examinations conducted during the previous thirteen years of operation have identified no degradation in these valves. The valves operate only infrequently and are thus not subject to significant wear between refueling outages. In addition, more fre@ent examination increases personnel exposure to loose radioactive materials, increases personnel radiation exposure, (total personnel exposure required to disassemble one valve is 3 to 5 rem), increases generation of radioactive waste, and could result in significant added costs. Northeast N'lclear Energy Company considers the proposed testing fully adequate to assure tho operability of this valve.
Northeast Nuclear Energy Company will continue to explore means to verify, physically, that the valve disk moves to the fully o conditions. pen If position under a practical    theof means  available testvalve verifying     flow disk position can be developed and the available test flow is sufficient to fully open the valve Northeast Nuclear Ener Company will full stroke test each valve each refueling. gy Howevor, Northeast Nuclear Energy Company requests the NRC reconsider the frequency of disassembly, inspection and exercise required to assure operability of these valves and approve the combination of a high flow test each refueling and a once-per-forty-months disassembly, inspection, and exercise. Relief Roquest RR-IWV-9 has been revised to
,             reilect this alternative testing and is included as Attachment 8.
: 8. Relief Request RR-IWV-15 states that the operators for valves 2-FW-12A and 12B can be exercised without an auxiliary feedwater flow, therefore the justification provided for not exercising those check valves with flow does not apply to the air operators used to facilitate valve operation. Do these powec operators perform any safety function? If so, these power operatore should be exercised, have their stroke times measured, and be fail-safe tested quarterly during power operations. These valves were discussed in Item F.1 of the IST working meeting held August 26 and 27, 1987.
RESPONSE - The power actuators on 2-FW-12A and 12B do not have a safety related function. These actuators receive no safety signal,

ATTACHMENT 1                                                              {
Page 6 of 8                                                               t
 .                                The actuator is connected such that it is an "open i                                permissive" device. However, even if the actuator failed to j                                function the auxiliary feedwater pump discharge pressure is
  !                               sufficient to open the check valve and provide full design flow.                                 Thus no testing of the actuators is required.
 !                 90     Relief Request RR-IWV-16 stetes that valves 2-RB-30.1A, 30.lB,
;                         37.2A, and 37.2B will be full-stroke exercised on cold shutdown 1                        when reactor coolant pumps are not running. Will the reactor                                                                                                                                 i coolant pur.ps be stopped every cold shutdown to facilitate testing                                                                                                                          ,
of these valves? The basis for relief in RR-IWV-16 does not                                                                                                                                  I identify tie negative effect of interrupting cooling flow to the                                                                                                                             j cooled components, provide this information.                                                                                                                                                ;
a                                                                                                                                                                                                                      ;
l"                RESPONSE - Northeast Nuclear Energy Company does not plan to stop reactor coolant pumps just to allow inservice testing to be                                                                                                                         ,
performed.                                                                                          If pumps are stopped in support of plant                                        i operations, testing of these valves will be conducted to the                                                                                                                        i" same extent and degree that all other valves scheduled for testing during cold shutdowns are tested.
i i                                Relief Request RR-IRV-16 has been revised to include the                                                                                                                             !
additional information requested and is included as Attachment 9.
 )                10. Relief Request RR-IWV-20 incorrectly categorizes valve 2-CH-431 as
 !                        Category B and indicates that it will be fail-safe tested and have
  ,                       its stroke time measured. 2-CH-431 appears to be a simple check 1
valve which should be categorized C and tested to the requirements
'                         of IhV-3520. This valve was discussed in Item H.2 of the IST working meeting held August 26 and 27, 1987
 )              RESPONSE - Valve 2-CH-431 was inadvertently included in the relief
~
1                                request with its corresponding air operated valve 2-CH-517.
To clarify the intent of the relief request, a separate Relief Request RR-IWV-33 and a revised Relief Request                                                                                                                                 ;
RR-IWV-20 has been provided as Attachment 10.                                                                                                                                         ,
i               11. Relief Request RR-IWV-23 states that valves 2-CH-198, 505                                                                                                                                 and    i 506 will be tested during cold shutdowns when reactor coolant pumps                                                                                                                          .
l                        are secured. Will the reactor coolant pumps be stopped every cold                                                                                                                            ,
  )
shutdown to facilitate testing of these valves?
RESPONSE - Northeast Nuclear Energy Company does not plan to stop reactor coolant pumps just to allow inservice testing to be                                                                                                                          ,
4                               performed.                                                                                           If pumps are stopped in Support of plant                                        l j                              operations, testing of these valves will be conducted to the                                                                                                                         (
same extent and degree that all other valves scheduled for                                                                                                                           !
testing during cold shutdowns are tested.
: 12.        Relief Requests RR-IWV-10 and 25 state that valves 2-SI-652 and 3                          651 respectively, will be tested during cold shutdowns when                                                                                                                                [
z.. actor coolant system pressure is less than 300 psig.                                                                                                                          Will the L j                         reactor coolant system pressure be reduced below 300 psig during                                                                                                                           l i
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ATTACHMENT 1 Page 7 of 8 every cold shutdown to facilitate testing of these valves?
RESPONSE - Northeast Nuclear Energy Company does not plan to reduce reactor coolant system pressure just to allow inservice testing to be performed. If pressure is reduced in support of plant operations, testing of these valves will be conducted to the same extent and degree that all other valves scheduled for testing during cold shutdowns are tested.
: 13. Relief Request RR-IWV-26 is a new relief request that has not been previously reviewed. This relief request does not provide sufficient information for a satisfactory evaluation.      Are penetration leak rates measured for any valves that have provisions for individual valve leak rate measurements? If so these valves should be individually leak rate tested as required.      Identify the groups of valves that are leak rate tested together.
RESPONSE - No valves that could be tested individually are tested as part of a penetration group. Relief Request RR-IWV-26 has been modified to identify those valves that are tested as part of penetration groups and is included as Attachment 11.
: 14. Provide a more detailed technical basis for not testing valves 2-MS-190A and 190B quarterly during power operation.      Relief Request RR-IWV-32 does not provide an adequate basis for not closing the manual isolation valves to allow performance of this testing. This was left open for the licensee to resolve as discussed in Item C.3 of the IST working meeting held August 26 and 27, 1987.
RESPONSE - No additional technical information beyond a restatement of the information already included can be provided.      Northeast Nuclear Energy Company considers that the Basis for Relief provided in Relief Request RR-IWV-32 clearly shows that closing the manual isolation valves to perform quarterly testing of valves 2-MS-190A and 190B, Waile not unsafe is imprudent.
However, since the NRC staff has rejected this proposed relief, Relief Request RR-IWV-32 has been cancelled.      A blank relief re@est is included as Attachment 12 to retain the administrative continuity of the documentation.      The appropriate valve listing changes have also been made.
: 15. The Testing Alternatives (QCS and FTCS) are not shown on the valve listing table for valves 2-MS-190A and 190B.
RESPONSE - The table has been revised to reflect the cancellation of Relief Request RR-IWV-32 (discussed above).
: 16. Does valve 2-RB-13.1A receive a remote indicator test?       If so this

ATTACHMENT 1 Page 8 of 8 should be indicated on the valve listing table.
RESPONSE - Yes                       valve 2-RB-13.1A does receive a remote position ind1cator test.            The valve listing table has been corrected.
Corrected pages are attached as part of Attachment 15.
: 17. Reactor vessel and pressurizer vent valves 2-RC-414, 415, 416, 417, 422, 423, 424, and 425 should be listed as valve type GL (globe                instead of relief valves? Relief re@est RR-IWV-21 does not lis)t 2-RC-425. Correct these program deficiencies.
RESPONSE - These typographical errors have been corrected. Attachment 13 is a corrected relief request. Corrected valve list                   ;
pages are included as part of Attachment 15.
: 18. Does the alternate testing proposed for the air supply check valves to the safety related instrument air accumulators satisfy all of the safety functions identified in the FSAR for the valves served by these accumulators.                       If not, propose alternate testing for these valves that verifies their ability to perform their saf=ty function. These valves were discussed in Item IV.1 of the IST working meeting held August 26 and 27, 1987.
RESPONSE         - The testing proposed for the air supply check valves to the safety related instrument air accumulators assures that all of the required safety functions of the valves will be met.          Since the original submission of this relief request i
additional actions have been taken to assure post-accident valve operability. Each valve is equipped with a readily replenished bottled air supply in addition to the accumulators. The emergency bottled air supply, which can be manually initiated from outside areas subject to high post-accident radiation levels is alone sufficient to meet all post-accident valve operab111ty requirements. The check valve leak test proposed will provided added assurance that the accumulator supply, combined with the j                                         emergency bottled air supply, will meet all post-accident valve operability requirements if the Instrument Air supply is lost. To reflect the added emergency air supply reliability the proposed leak test has been revised. In               ,
:                                       addition one valve not required to be operable during                 L I
accident or post accident conditions has been deleted. The revised submittal page is included as Attachment 14.
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Docket No. 50-336 A07351 Attachment 2 Table IWP August 1988

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DE.82t No. 50-336 AG7351 a
o Attachment 3 Service Water Pump Vibration August 1988

ATTACHMENT 3 Page 1 of 2 JUSTIFICATION FOR HIGHER ALLOWABLE VIBRATION LEVELS MILLSTONE UNIT 2 SERVICE WATER PUMPS Service Water Pump (SWP) vibration measurements are taken at the top of the motor rather than on the pump casing as recommended by OM-6 to provide a more sensitive indicator of overall pump / motor condition. The pump operates at relatively slow speed (900 RPM). The pump casing is solidly mounted to the screen house floor. The pump bearings are (relatively) large clearance water lubricated bearings.
These factors make vibration measurements taken on the accessible pump casing less sensitive to overall pump condition.                        .
Because of their unique dynamic characteristics, the Service Water Pumps normally operate at relatively high vibration amplitudes of 0.3 to 0.6 inches /second velocity as measured at the top of the motors. While vibration levels are significantly lower at points on the pump housing, motor vibration levels are routinely monitored to provide early warning of significant pump / motor degradation. Accordingly, a "service f actor" has boon applied to increase the Alert level from 0.325 to 0.65 inches /second and the Required Action level from 0.7 to 1.4 inches /second.
The service factor recognizes the higher operating vibration levels caused by the unusually tall structure (11' above the foundation), very flexible motor support stand, and lack of external support at the top of the motor housing. The Hydraulic Institute standards for centrifugal pumps allow vibration levels of new, tall, vertical pump units to be almost twice as high as equivalent horizontal pumps. Despite the higher vibration levels, the magnitude of mechanical degradation (i.e. rotor unbalance, misalignment, etc) will be no greater than for other equipment with normal support flexibility operating at the lower vibration limits.
Restated, for a given amount of cquipment degradation, upper motor vibration levels will be more than twice the levels of a "standard" pump.
Another significant factor which translates to lower vibration severity for a given vibration amplitudo is that the fundamental resonant frequency of the pump structure is only 10 percent away from running speed. This means that any vibratory forces with a frequency coinciding with running speed [the predominant force) will cause over twice as much vibratton as compared to the normal pump with 25 percent minimum margin from resonance. No attempt has been made to justify higher vibration limits based on the resonance phenomena.
Reliable operation at the higher vibration levels is further assured by the advanced nature of the Millstone Unit 2 vibration monitoring program which is capable of detecting problems at an early stage, identifying probable causes and monitoring trends such that corrective maintenance can be scheduled well in advance of a serious degradation or failure.
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ATTACHMENT 3 Page 2 of 2 ACTIONS For additional assurance of reliable operation, in addition to actions rapired by the ASME Boiler and Pressure Vessel Code the following actions will be implemented:
: 1. Determine baseline pump shaft vibration level after each pump overhaul.
: 2. Whenever the pump is operating in the Alert Range:
: a. Verify the upper motor vibration signature is normal (i.e. predominantly running frequency and harmonics of running frequency). Abnormal vibration characteristics such as motor bearing related vibration will be evaluated and corrective action taken to avoid serious degradation or failures.
: b. Check pump shaft vibration during each required pump test,
: c. Remove the pump from service if upper motor vibration exceeds 1.4 inches /second or pump shaft vibration exceeds 30 mils (peak to peak) s

Docket No. 50-336 A07351 Attachments 4 through 13 Revised Relief Requests l
August 1988 i
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ATTACHMENT 4                              '
Page 1 of 3 Millstone Nuclear Power Station Unit No. 2                 ;
Second Ten-Year Interval                        l
           ' Relief from In-Service Testing Requirements               ,
Relief Reauest:     RR-IWP-1 (Rev. 1)
Pump Vibration Monitoring In-Service Test Pume Identification!
ASME Code Class 2 and 3      Category:   IWP Aeolicable Pument All pumps as shown on Table IWP Pumo Function Centrifugal and positive displacement pumps that are required        t to perform a specific function in shutting down the reactor          i or in mitigating the consequences of an accident.
Code Reauirement:
Table IWP-3100-1 and IWP-3100-2, of the 1980 Edition, Winter         ,
1981 Addenda requires that vibration amplitude be measured.          ;
Paragraph IWP-4510, requires that at least one displacement          ,
vibration amplitude (peak to peak composite) shall be read           l during the in-service test.
Code Relief Reauestedt                                               ;
Relief is requested from measuring the overall vibration             [
amplitude in mils.                                                   F Basis for Relieft                                                    .
Experience has shown that measurement of overall vibration           l amplitude in mils does not provide the desired early warning         i of pump degradation. Vibration amplitude is adequate for             I I
measuring unbalance, misalignment, and other low frequency failure modes. It does not give early warning of bearing             '
degradation since the magnitude of higher frequency vibration created by such degradation is 10 to 1,000 times lower than          i the normal pump movements. Experience at Northeast Utilities has shown that monitoring pump vibration velocity (in/sec)           ,
provides earlier warning of pum degradation. Collection and          i review of vibration "signatures ' (Plots of vibration velocity vs. frequency) over a range from slightly below running              !
frequency to several times running frequency provides optimal early warning of pump degradation.                                   ,
Absolute maximum limits are set for each pump.       Higher          i maximum limits are appropriate for the Service Water Pumps           (
since the measurements taken at the upper motor bearing              ;
housing are significantly affected 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            j t
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  , ..  .                                                                                                 1 ATTACHMENT 4 Page 2 of 3 resonance frequency is within10 percent of the running frequency. Millstone Unit 2 experience har shown that the pump vibration levels are extremely sensitive to small amounts of unbalance or pump shaft bearing loosonoss.
Inspections have shown minimal pump or motor degradation after extended operation at vibration levels near the proposed maximum allowable levels.       Because of those factors, a "service factor" of 2 has boon assigned to the vibration limits for those pumps and the maximum allowable vibration adjusted accordingly.
Pronosed Alternative Testino:
For contrifugal pumps, at leas't two measuromonts will be taken in a plano perpendicular to the rotating shaft in two orthogonal directions and eno measurement taken in the axial direction.
For reciprocating pumps, similar measuromonts will be taken on a bearing housing of the crankshaft.
On vertical lino shaft pumps      measuromonts will be taken on the upper motor bearing hous1ng in three orthogonal directions including one axial direction.
Vibration will be monitored using equipment which collects vibration signatures over a range from less than one-half running speed to at least eight times running spood, overall vibration velocity will be compared to the following acceptance critoria for all but the Service Water Pumps:
Acceptablo Range = less than 2.5 times reference velocity Alert Range - 2.5 to 5 times reference velocity but not greator than 0.325 in/sec (peak)
Required Action Rango - greater than 5 times reference l                                        velocity but not greater than 0.70 in/ soc (Poak)
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:
Alert Rango >0.65 in/sec (peak)
Required Action Range - >1.4      in/sec (Poak)
In addition to the abovo quantitative analysis of overall vibration lovcis, 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.

ATTACHMENT 4 Page 3 of 3 In addition, when pump vibration levels are in the Alert Range, pump shaft displacement measurements will be made whenever pump vibration measurements are required. These measurements taken directly from the pump shaft rather than the relatively stiff pump casing or bearing housing are most indicative of the actual pump condition. Pump shaft dis lacement levels are normally about 10 mils. Pump shaft dis lacement will be limited to 30 mils (peak to peak).
Pro onged operations with shaft displacement above this level can result in excessive pu p seal wear or pump bearing damage. If pump shaft dis lacement exceeds 30 mils peak) the pump will be dec ared in the Required Actio(peak to n Range 1
and appropriate corrective actions taken.
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ATTACHMENT 5 MILLSTONE NUCLEAR POWER STATION UNIT No. 2 SECOND TEN-YEAR INTERVAL                                                                                          i i
Relief from In-Service Testing Requirements Relief Reauest:                        RR-IWV-3 (Rev. 1)
Containment Spray Header Check Valves 2-CS-SA and 2-CS-5B
 !                                                           Comoonent Identification:
ASME Code Class:                     2                                                                                                           !
IWV 2200 Valve Category:                          AC                                                                                             j d
Valve Function                                                                                                                                           ;
t check valves in containment spray header inside                                                                                                   l containment. Serve as inside containment isolation valve                                                                                         ;
on a line which is open to containment atmosphere and                                                                                             !
penetrates the containment boundary.                                                                                                              ,
i Code Recuirement:                                                                                                                                         l Article IWV-1000 requires that the valves be exercised                                                                                           l (full stroke) quarterly.                                                                                                                          '
I
 !                                                           Code Relief Recuested:
r Relief is requested from performing the full stroke test                                                                                          i i                                                                    during plant operation, cold shutdowns and refuelings.                                                                                           !
j                                                            Basis for Relief Valve operation cannot be verified during reactor I-                                                                                                                                                                                                                   '
operations since the valves are inaccessible during
 .                                                                   plant operation. Water cannot be used for this test                                                                                              ,
i '
since massive containment wetting would occur if full or partial flow was passed through this valve. Thus the                                                                                             f
;                                                                    valve cannot be tested with fluid flow under any plant                                                                                            l conditions.                                                                                                                                       ;
Proposed Alternative Testino:
l One valve will be disassembled, inspected and manually                                                                                           [
exercised during each refueling outage.                                                                                                          ;
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ATTACHMENT 6 MILLSTONE NUCLEAR POWER STATION UNIT No. 2 SECOND TEN-YEAR INTERVAL Relief from In-Service Testing Requirements i    Relief Recuestt              RR-IWV-4 (Rev. 1)
Containment Spray Refueling Water Storage Tank Header (RWST) Check Valves 2-CS-14A and 2-CS-14B Component Identificatient ASME Code Class:             2 IWV 2200 Valve Category:             C Valve Functiont check valves to prevent backflow from safety injection
;           suction header to the RWST.
1 Code Recuirement:
Article IWV-3000 requires that this valve be exercised (full stroke) every three months.
Code Relief Recuestedt Relief is requested from performing the required exercise (full stroke) test every three months during plant operation.
Basis for Relieft
!                                                                                                                           reactor Valvecannotbefullstrokeexerciseddurin$ntothe operation since the only full flow path is
 ,          reactor coolant system.              Safety injection pump discharge pressures are not adequate to admit water to the
;           pressurized Reactor Coolant System. The only flow path capable of accepting full design flow is from the
!           Refueling Water Storage Tank into the Reactor Coolant System via the Low Pressure Safety Injection pumps.                                                                     Use
:           of the Containment Spray pump would not fully stroke the valvo and would result in massive containment wetting and consequent equipment damage. Valve cannot be full stroked during cold shutdown since over-pressurization j           of the Reactor Coolant System would result.
I      Proposed Alternative Testingt 1
l           Valve shall be part stroke exercised quarterly and full 1
stroke exercised at each refueling.
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ATTACHMENT 7 MILLSTONE NUCLEAR POWER STATION UNIT NO. 2 SECOND TEN-YEAR INTERVAL Relief from In-Service Testing Requirements Relief Recuest:   RR-IWV-8 (Rev.1)
Safety Injection System Valves 2-S1-215, 225, 235, and 245 Component Identification:
ASME Code Classtl IWV 2200 Valve Category:   C Valve Function:
Prevent backflow into the safety injection tank. Allow rapid discharge of the safety injection tank in the event of a loss-of-coolant accident.
code Requirement:
IWV-3522 requires that those check valves be exercised to the position required to fulfill their function quarterly during plant operation.
l Code Relief Reauested:
Relief is required from quarterly test, testing during cold shutdown, and full stroke testing during each refueling.
Basis for Relief:
Valves cannot be full stroke exercised during reactor operation or cold shutdown since no flow 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 consequent plant shutdown. Further, if the valve failed to rescat only single valve isolation would exist betwoon the reactor coolant system and the low pressure safety injection tank. The flow rates available through the small diameter test line would not result in signficant operation of the valves during operation or cold shutdown.
Proposed Alternative Testino:
Full stroke exercise each valve once per refueling if practicable. If unable to full stroke exerciso each valve, one valve will be disassembled, examined, and manually stroked every forty months.

ATTACHMENT 8 MILLSTONE NUCLEAR POWER STATION UNIT NO. 2 SECOND TEN-YEAR INTERVAL Relief from In-Service Testing Requirements Relief Roauest!   RR-IWV-9 (Rov. 1)
Safety Injection System Valvos 2-SI-217, 227, 237, and 247 Comnonent Identification ASME Codo Class:   1 IWV 2200 Valve Category:  C Valve Function!
Provent backflow into the safety injection heador.
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.
Codo Roauirement:
IWV 3522 requires that those check valvos be exercised to the position required to fulfill their function quarterly during plant operation.
Code Relief Reauested:
l Relief is requested from quarterly test, testing during cold shutdown, and full stroke testing during each refueling.
Basis for Relief Valves cannot be full stroke exorcised during reactor operation or cold shutdown since there is no pressure source able to overcomo Reactor Coolant System Pressure which can fully open the valves. Valves cannot be part stroke tested during reactor operation since injection of cold water would result in an unacceptable thermal I
shock to the safety injection nozzle. Valves cannot be full stroke tested during cold shutdown and refueling sinco there is no source of water able to provide full design flow.
Ersposed Alternativo Testina:
Full stroko exorciso each valvo each refueling if practicable. If each valvo cannot be full stroko
,                                                  exercised one valve will be disassembled, examined and I
manually stroked each forty months.

ATTACHMENT 9 MILLSTONE NUCLEAR POWER STATION UNIT NO. 2 SECOND TEN-YEAR INTERVAL Relief from In-Service Testing Requirements t
Relief Reauest:   RR-IWV-16 (Rev.1)
Reactor Building Closed Cooling Water Check Valves 2-RB-30.lA, 30.1B, 37.2A and 37.2B Comoonent Identification:
ASME Code Class:     2 IWV 2200 Valve Categoryt    B Valve Function To isolate miscellaneous containment heat loads.
Code Reauirementt i
IWV-3000 requires that these valves be exercised (full stroke) and stroke time measured every three months.
]     Code Relief Recuestedt 1
i          Relief is requested from performing the required exercise and stroke time measurement every three months
:          during plant operation.
1 i     Basis for Relieft
>          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. Interruption of cooling water flow to operating reactor coolant pump thermal barriers even for short periods can result in rapid degradation of sh.sft seals and/or seal failure.
Other loads though slightly less sensitive to flow perturbations, could also be adversely affected if a valve failed to fully reopen during testing. Valve design precludes part stroke exercising.
Ergposed Alternative Testing:
Valve will be full stroke exercised on cold shutdown when reactor coolant pumps are not running.
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ATTACHMENT 10 Page 1 of 2 MILLSTONE NUCLEAR POWER STATION UNIT NO. 2 SECOND TEN-YEAR INTERVAL Relief from In-Service Testing Requirements Relief Reauest                         RR-IWV-20 (Rev. 1)
Chemical and Volume control Globe Valve 2-CH-517 i                                               Conconent Identification ASME Code Classtl IWV 2200 Valve category                B Valve Function To provide flow to pressurizer vapor space during
;                                                                          depressurization.
Code Recuirementt j                                                                        IWV-3000 requires that this valve be exercised (full
;                                                                        stroke), fail tested, and the stroke time measured every l                                                                        three months.
l                                               Code Relief Reauestedt 1
j                                                                        Relief is requested from performing the required i                                                                        exercise and stroke time measurement every three months during plant operations.
l                                               Basis for Relieft I
]                                                                        Valve exercise during reactor operation could cause loss l
of reactor coolant system pressure control with i                                                                        consequent plant shutdown and/or excessive thernal a                                                                        transients on the pressurizer spray piping.
Pronosed Alternative Testinct Exercise full stroke), fail test, and measure stroke
 !                                                                       time durin(g cold shutdown.
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1 ATTACHMENT 10 Page 2 of 2                                                                                        ;
MILLSTONE NUCLEAR POWER STATION UNIT NO. 2 SECOND TEN-YEAR INTERVAL Relief from In-Service Testing Requirements Relief Recuest:                 RR-IWV-33 (New)
Chemical and Volume control Check Valve                                                                                             '
2-CH-431 Comoonent Identification:
ASME Code Class:1 IWV 2200 Vulvo Category:                 C Valve Function:
To provide flow to pressurizer vapor space during depressurization.
Code Requirement:
IWV-3000 requires that this valve be exercised (full stroke) three months.
Code Relief Recuested:
Relief is requested from performing the required exercise every three months during plant operations.
Basis for Relief:
Valvo exercise 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.
Proposed Alternative Testino:
Exercise (full stroke) during cold shutdown.

ATTACHMENT 11                                                                                ,
Page 1 of 4 MILLSTONE NUCLEAR POWER STATION UNIT NO. 2 SECOND TEN-YEAR INTERVAL Relief from In-Service Testing Requirements Relief Reauestr            RR-IWV-26 (Rev. 1)
All Class 2, Category A and A Passive (AP) Containment Isolation Valves for applicable valves, see attached                                                                     ;
list.
Comoonent Identificationt ASME Code Class:            2 IWV 2200 Valve Categories:              A and AP Valve Functiont To insure containment integrity in event of requirements to isolate.
Code Reauirementt IWV-3424 requires valve seat leakage be determined by measuring the feed rate required to maintain pressure between two valves or between two seats of a gate valve, provided the total apparent leak rate is charged to the valve or gate valve seat being tested, and that the conditions required by IWV-3423 are satisfied.
d Code Relief Reauestedt i
Relief is requested from the requirement of IWV-3424b, determined by measuring the                                                        '
that feed valve       seat leakage,intain rate required     to ma       pressure between two valves, be charged to a single valve.                                                                                   >
Relief is also requested to use an alternative test                                                                     i
!                     technique based on pressure decay rate between isolation i
valves when leakage exceeds the measurement limits of feed rate measuring devices.                                                                                            ,
t Basis for Relieft i
The proposed alternative testing and alternate test technique comply with the requirements of Appendix J in 10CFR50.
Some piping systems are not configured to allow single valve testing. The proposed alternative test provides                                                                   j assurance that total containment leakage remains within i                     limits yet allows trouble shooting to identify
:                     individual leaking valves without requiring                                                                             ,
t                     quantification of leakage through a single valve.                                                                       i f
Valves for which multiple valve testing is required are indicated by superscripted group numbers in the attached list.         All valves are included in the request for i                                                                                                                                             i r
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ATTACHMENT 11 Page 2 of 4 i
alternate leakage measurement techniques when leakage                                                      '
exceeds standard leakage measurement equipment capabilities.
Proposed Alternative Testina!                                                                                   ,
Leak Test category A valves in groups when single valve testing cannot be accomplished. Where multiple valves on a single penetration are tested in a single test, the leakage will be attributed to the penetration not to an                                                   l individual valve. Analysis of leakage rate and establishment of maximum allowable laak rates for these valves will be based on total penetration leakage.
Analysis and corrective action will be in +:cordance                                                      ,
with IWV-3426 and 3427.
* l Where leakage rates exceed measurement limits of feed rate measuring devices an alternative test based on                                                       l pressure decay rate between isolation valves will be                                                      i used.                                                                                                     !
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ATT/ <' 'MFMT 11 Pags 3 .:t 4 LIST UC AI
* A'ABLE VALVES Valve      Class /                    Valve         Class /
Number     Category                   Number        Category 2-CH-4291     2A                      2-FIRE-108       2AP 2-AC-47       2A                       2-CH-198        2A 2-AC-51        2AP                     2-CH-505        2A 2-EB-88       2A                       2-RW-154 M     2AP 2-EB-89        2A                      2-RW-232'       2AP 2-EB-91"     2A                       2-SSP-16.1      2A 2-EB-92"     2A                       2-SSP-16.2      2A 2-EB-9912    2A                       2-AC-4          2AP 2 EB-LOO 12  2A                       2-AC-5          2AP 2-SA-19        2AP                     2-AC-6          2AP l   2-CH-506      2A                       2-AC-7          2AP 2-CH-516      2A                       2-AC-12         2A 2-CS-4.1A     2A                       2-AC-15         2A 2-CS-4.1B     2A                       2-AC-20         2A 2-S1-312       2A                      2-MS-220A 3     2A 2-SI-463      2AP                      2-MS-220B'      2A 2-SI-709 2    2AP                     2-GR-11.1 6     2A 2-MS-191A3    2A                      2-GR-11.2'      2A 2-MS-191B'    2A                      2-LRR-43.15     2A 2-PMW-43       2A                      2-LRR-43.25     2A 2-FIRE-109     2A                      2-LLR-61.1      2A 2-RC-OOl       2A                      2-RW-21'        2AP 2-RC-002       2A                      2-RW-634       2AP i

ATTACHMENT 11 Page 4 of 4 Valve              Class /                         Valve            class /
Number             Category                        Number           Category 2-RC-003               2A                            2-CH-5171          1A 2-RC-45                2A                           2-CH-5181           1A 2-CH-089               2A                           2-CH-5191           1A 2-1A-27.1             2A                            2-AC-46             2AP                                                     l 2-AC-1128             2AP                         2-AC-1147            2AP 2-AC-116s             2AP                         2-AC-54              2A 2-AC-1177             2AP                         2-AC-55              2A                                                      l 2-RB-37.2A            2A                            2-RB-37.2B          2A 2-RB-30.1A            2A                             2-RB-30.1B         2A 2-CS-5A               2AC                            2-CS-5B            2AC 2-SI-6512             1A i
NOTE:   Superscript numbers indicate valve groupings                                                                           I when testing limits are based on penetration leakage rather than single valve leakage I
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s                                                          i ATTACHMENT 12                 (
l i             MILLSTONE NUCLEAR POWER STATION UNIT No. 2   i SECOND TEN-YEAR INTERVAL Relief from In-Service Testing Requirements l 1
Relief Request   RR-IWV-32  (CANCELLED) i                                                            !
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ATTACHMENT 13 MILLSTONE NUCLEAR POWER STATION UNIT NO. 2 SECOND TEN-YEAR INTERVAL Relief from In-Service Testing Requirements Relief Reauest    RR-IWV-21 (Rev. 1)
Reactor Coolant System Venting Solenoid Valves 2-RC-414, 415, 416, 417, 422, 423, 424, and 425 Component Identification:
ASME Code Class 1 IWV 2200 Valve Category:   B Valve Functiont To provide venting of reactor coolant system.
gode Reauirement:
IWV-3000 requires that these valves be exercised (full open position) every three months.
Code Relief Recuested:
Relief is re@ested from performing the required exercise during plant operations every three moeths.
Basis for Relieft_
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 inprudent to violate the two valve barrier solely to verify operability of these valves.
Proposed Alternative Testingt Exercise full stroke during cold shutdowns.
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Docket No. 50-336 A07351 Attachment 14 Safety Related Instrument Air Accu olations I
Aegust 1988 i

s-ATTACHMENT 14 g                     SAFETY-RELATED INSTRUMENT AIR ACCUMULATO".o Valve (s) Served                        7 unction          Test 2-AC-15           Containment Purge Iso'.ation       LTl 2-AC-20           Containment Purge isolation        LT l 2-S1-659          Safety Injection Minimum flow      LT l Recirculation Isolation 2-SI-660          Safety Injection Minimum flow      LT 1 Recirculation Isolation 2-CH-517          Auxiliary Spray Isolation          LTl 2-CH-518          Loop Charging Isolation            LTl 2 -CII-519        Loop ClMrging Isolation            LT 1 NOTE 1:           This leak test will be performed on the air supply check valve to the accumulator each refueling. The test shall verify that the accumulator will retain sufficient air to provide operation of the valve for 1 hour after loss of instrument air, instead of method specified in IWV-3424.
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Docket No. 50-336 A07351 Attachment 15 Corrected Valve List Pages August 1988 l

1 ATTACHtENT 15                                                            -
(IWW)
Test       llelief   Test.ing Velve            Normel Feedmeter Stre                               Requirements Seesests Alternative Class /                                                     Actuetten Pos9 tion                                   .
Volvo Category   25203-26126. Sh. 4               (Inches)   h Nueer_                                                                                               0
                                                                              -         C Terry Aun. FW Pump Rectrc. Owck        1.5     CF 2-FW-33         3C A0        C            0 4      CL 38    Aux. FW Reg. Valve to No.1 S.C.                                                Pt 2-FW-43A A0        C           0 4      CL 38 Aux. FW Reg. Valve to No. 2 S.C.                                         -
98 2-FW-438 NO        C            0 6      CA 38    Aum. FW Pump Dis. Cross Tfe                                                    PI 2-FW-44 H        C            0 6      CA 38    Aux. FW Reg. Valve dypass 2-FW-56A H         C            0 6     GA 38   Aux. FW Reg. Valve Sypass 2-FW-568 re84/611136

                            ;                                                                                                      R (IWV)               '
Test       Relief    Testing Normel Size     Velve                        Aequirements  Roguests Alternettve Class /        Service Water                           Actuetten Position _
Velve Category    25203-26126. Sh. 7 (Inches)   h                                                                 .
teusdner_
                                                                           -          0             0 24      CK 3C SW Pump A Discherge Check 2-5W-tA                                                                                            0 CK
                                                                           -           0 24 3C SW Pump 8 Discharge Check 2-5W-18                                                                                            0 CK
                                                                            -          0 24 3C   SW Pump C Discharge Check 2-5W-1C                                                                                     -
0 BFLY       A0         0 16                                          FT 38   8 SW Header to TBCCW HKs 2-5W-3.2A                                                                                           Pt A0         0            0 16      BFLY "A" $W Hoeder to TBCCW HIs                                                  FT 2 & -3.28         38 PI A0         0            0 18      BFLY 38    A IIBCCW HK Temp. Control                                                   FT 2-5W-8.1A A0         0            0 18      BFLY 8 RBCCW HK Temp. Control                                                    FT 2-5W-8.18          38 A0         0            0 18     BFLY C IISCCW HK Temp. Control                                                    FT 2-5W-8.1C         38                                     .
re84/611136

r                          ,
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Test           me11ef     Testtag Velve                     Mermal Service Water                 Size                                 pos{tlen  Segsfrements       Regeests Alternettwo Velv,           Ctess/                                    (Inches)      g         Actuation                                                         .
mW             Category    25203-26126. Sh. 7
                                                                                          -              0             0 24          CK 3C A Otscherge Header O eck 2-5W-11 A 0             0 24         CK 3C    8 Discherge Heeder Check 2-55-118
                                                                                           -              C            0 8         CK 3C    A Diesel Cooling Discharge 2-55-13A
                                                                                           -              C     -
0 8          CK 3C   8 Diesel Coeling Discharge 2-55-138 A0             C             0 6          SFLY 38   A Diesel Coeling Temp. Control                                                              FT 2-5W-09A PI A0             C            0 8 Diesel Coeling Temp. Control         6         8 FLY FT 2-55-898         38 FI A0           0             0 2         CL 2-5W-102          38     A SW Header to Oillier X-170                                                              FT PI A0           0            0 2         CL 36     8 SW Heeder to Ollier X-170                                                                FT 2-5W-104                                                       .
Pt A0           0              0 8         BFl.Y 38    A Diesel Coeling Sypass                                                                      FT 2 5W-231A PI A0           0               0 8        SFLY 38     8 Diesel Coeling Sypass                                                                      FT       ,
2-54-2318                                                                                             "               Pl re84/611136                                                                                                             .
3                                                                                                                               _

                                      ~
I                                                                                                                                                          7 (IW)
* Test        IIelief                                      Testing Velve                    Normal Contetrument Spray                   5fre Seefrements   Re gests                          Alternettve Velve            Class /                                                      g        Actuetton      Position 25203-26126. Sh. 3                 (Inches) w               Categor_r
                                                                                  ~
0 CK
                                                                                           -              C 8
2C      C5 Pump A Discherge 2-C5-2A
                                                                                           -              C             0 8          CK 2C      C5 Pump 8 Discharge 2-C5-28                                                                                                                          IIIt-lW-3
                                                                                            -              C            0 8         CK                                               IIIt-lW-26                                      LLRT 2AC     C5 Hoeder A Check                                                                           LT 2-CS-5A
                                                                                             -             C             0       stit-lW-3 8         CK                                                IIIt-lW-26                                     LLRT 2AC     C5 Heade.- a Check                                                                          LT 2-C5-58
                                                                                             -             C             0 2         CK 2C      C5 Pump A necfre.
2-C5-6A
                                                                                             -             C             0 2         CK 2C      C5 Pump B Ilocfrc.
2-CS-68 M0            0            0 18         CA 28     ItWST Heeder A Isotation                                                                     Pt 2-C5-13.1 A M0           O             O 13          CA 28      ItWST Heeder B isolation                                                                    Pt 2-C5-13.18
                                                                                               -             C            0        Itit-lW-4                                      OP 18         CK                                                                                              Ost 2C     IlWST Heeder A Check 2-CS-14A
                                                                                                -            C             0        lilt-lW-4                                     OP 1kl         CK                                                                                              Olt 2-C5-148            2C      stWST Hooder B Check
                                                                                                 -           C             0        IIIt-lW-5                                      OP 24         CK                                                                                              DET 2C       CTMT Sump Outlet Heeder A Check 2-CS-15A
                                                                                                  -           C            0         IIR-lW-5                                      OP 24          CK                                                                                             DET 2C CTNT Sump Outlet Hoeder 8 Check                                                                      ,.
2-CS-153 MD          C             0 24         CA 28       CTNT Sump Outlet Hoeder A                                                                 PI 2-CS-16.1 A MD          C            0 24         CA 28        CTMT Sump Outlet Header 8                                                                PI 2-CS-16.18                                                                                                                                                               ,-      -
re84/611136

o
                                                                                                                                          .(IWW)                          1-Valve         Class /    meactor Building Closed Cooling        Size        Valve                    normel          Test                Rollef-            Testin8 uumber       Category       mater 25203-26126. Sh. 6          (Inches)      h            Actuation  Position     Requirements           Requests          Alternettwo   ,I i
2-AB-2A         3C    Pump A Discnerge                           20           CK             -
0                    0 2-M-28          3C    Pump B Discharge                           20           CK             -
0                    0                                                     ,
                                                                                                                                                                              ~
2-RS-2C         3C    Pump C Discharge                           20           CK.            -
0                    0 i
                                                                                                                                                                        'l 2-M -4.1A       38    SFPC HK and 8. A. Evap. Outlet              12          BFLY           A0         0                    0                                         t FT                                         j PI                                         i 2- 5-4.18       38    SF8C HX and 7. W. Evap. Outlet              12          BFLY           A0         0                    0                                                     j FT Pt 2-5-13.1 A      38    SD Cooling HX A Outlet                      18          BFLY           A0         C                    0 FT PI                                         2 t-;
i 2-R8-13.18      38    50 Cooling HK 8 Outlet                      18          BFLY           A0         C                    0 FT PI                                         ,
4
                                                                                                                                                                          ?
2-M-28.3A        28   IWCCW From CAR Cooler A                     10          BFLY           A0         C                    0 FT                                        .
Pt 2-RS-28.38      28   RBCCW From CAR Cooler 8                     10          BFLY           AC         C                    0                                         t FT                                        <
PI 2-NB-28.3C      23   marrw From CAR Cooler C                     10          BFLY           A0         C                    0                                                     ;
FT                                                    [
PI 2-5-28.30      ,13    IIBCCW From CAR Cooler D                   10          SFLY           A0         C                    0-                                                     -
FT PI                         ,
f i
re84/611136                                                                                                                                                    ,           !
h.
I 1

(lW)                                                    ,
Test       Reifef                                      Testing Normel Size     Velve                        Requirements Reg;sests Alternettve Reactor Building Closed Cooling                        Actuation Position Velve          Class /
Water 25203-26120. Sh. 6 _      (Inches)   g                                                                                                   .
Category seumber_
O           O      ite-IW-16                                      0CS MO RBCCW to RC Pump Coolers et al.            8        CA Pl     M-lW-26                                        LLRT 2-b-30.1A        2A LT O           O       IIR-lW-16                                     OCS 6       CA          MO RBCCW to RC Pump Coolers et al.                                                       PI      ItR-lW-26                                      LLRT 2- 5 -30.18      2A LT O       stR-lW-16                                     OCS CA          MO        O IIBCCW From RC Pump Coolers et al.         8                                          Pl      Illt-IW-26                                    LLRT 2-RB-37.2A       2A LT O           O       stR-lW-16                                      0CS 6       CA          MO IIBCCW From RC Pump Coolers et al.                                                    PI     IIR-lW-26                                      LLRT 2-115-37.18      2A LT A0        C           0 2        CL 38     Eng. Safeguerds IDS Cooler Outlet                                                    FT 2-ItB-68.1A 98 A0        C           0 2       C'_
38      Eng. Safeguards IDI Cooler Outlet                                                   FT 2-5-6C.18                                                         .
Pt A0        C           0 8        BFLY 2-1t8-210        35      Degastfler Return Stop                                                              FT                                ,
PI re84/611136

I 1
(IW)               ,,
Test         Rollef     Testing Valve              Mormel Mein Steam Size Position Requirements   Requests Alternative Velve          Class /                                             (Inches)        h       Actuation
                                                                                                                                                       ~
25203-2%126. Sh. 2 wr_           Category
                                                                                                 -         C           0        Ita-lW-30     OCS 4           CK                                                      OP 3C Aux. Fu Turbine Suppif Check 2-MS-4A
                                                                                                 -         C           0        IIR-lW-30     OCS 4            CK                                                     OP 3C Aux. FW Turbine Supply Check 2-MS-48 0    -
0         IIR-lW-1      OCS 34            STOP       A0                                           OP 28     No. 1 MSIV                                                                                  PI 2-MS-64A                                                                           CK                                                      FTCS FT 0           0         Ita-IW-1     OCS 34             STOP       A0 PI                     QP 28     No. 2 MSIV 2-MS-648                                                                            CK R                      RG C           0        stR-lW-2      OCS Cl.        NO 3                                            Pt 28     No. 1 MSIV Bypass 2-MS-65A C           0         stR-lW-2     OCS
: 08.        NO 3                                            Pi 28    No. 2 MSiv Bypass 2-MS-658
}                                                                                                   A0        C          0 S           CL 23     No.1 S.C. Atmospheric Dump                                                                  FT I     2-MS-t?OA PI 1
q          g        C           0 8
23    No. 2,S.C. Atmospheric Dump                                                                 FT 2-MS-19CP.
Pi MO        O           O 4          CA 28     No. 1 S.C. Supply to Aux. FW Turbine                                                        PI        .-
a-MS-201 4           CA 28     Iso. 2 S.C. Supply to Aux. Fw Turbine                                                      pg 2-MS-202 1
i                                                                                .
1 re84/611136                                                                                                           .

(IW)
Test       IIellef . Testing Valve            IIormal Main Steam                                  Stre                                Requirements Requests Alternative Valve           Class /                                                                  g     Actuation Position 25203-26126. Sh. 2                            (Inches)                                                                .
as.h_          Category M0         C          0 4         CL 38        Steam to Auz. FW Turbine                                                                    Pt SV-4198 A0          0         0 1        CL 2-MS-2658          38        Steam Drain Isolation                                                                      FT Pl A0         0          0 1         CL 2-MS-2668         38        Steam Draln isolation                                                                       FT Pt itit-IW-27    *
                                                                                                            -           0         0 34         CHK 2-MS-1A            3C       Mein Steam Monreturn Check Valve Itt-lW-27     *
                                                                                                            -           0          0 34         CHK 2-MS-18           3C       Mala Steam Nonceturn Check Valve
           *5ee Relief Request stit-lW-27 r
i 1
l 1
f                                                                                                                                           .-
I
:l l
l                                                                 -
1
\                                                                                                                                                    .
i 4
i I             re64/611136 1

2 1
(IW)
* Test           Reifef           Testing Normat Size            Velve                            Requirements     Requests    Afternettwo Class /        Reector Coolant                                        Actuetton    Post tf ore Velve 25203-26126. Sh. 11 (Inches)          h                                                                             .
u.*r           Category C             SRV 2.5           ItEL       -
2-RC-200          1C       Pressurfzer Reifef
                                                                                            -              C             SRV 2.5            REL 2-RC-201           1C      Pressurtzer Rollef C             SW REL        SOL 2.5 1C      Pressortzer PORY 2-AC-402                                                                                                               SW REL        SOL          C 2.5 1C      Pressurizer PORY 2-RC-404                                                                                                               0         RR-lW-21           OCS CL         50L           C
                                                                     .75                                                  Pt 18      Reactor Vessel Vent 2-RC-414 C            0          M-IW-21           OCS
                                                                      .75          CL         SOL Reactor Vessel Vent                                                                         Pt 2-RC-415           15 0         RR-lW-21           OCS CL         SOL           C
                                                                       .75                                                 Pt 2-RC-416           18     Reector Vessel Ysot C             0         ItR-lW-11          OCS
                                                                       .75          CL         SOL Reector Vessel Vent                                                                         Pt 2-RC-417           18 C            0          M-lW-21            OCS CL         SOL
                                                                        .75                                                 Pt 2-RC-422            18     Pressurizer Vent C             0         Itt-lW-21          0C5 CL         SOL
                                                                         .75                                                Pt 2-RC-423           15     Pressurfrer Vent 0         RR-lW-21            OCS CL         SOL            C 75 18     Pressurtzer Vent                                                                             Pt 2-RC-424 C             0         RR-IW-21           OCS CL          SOL
                                                                          .75                                                PI 2-RC-425           15     Pressurtzer Vent h tfwe the pressurizer is filled NOTE 13 in additloc to testis.g In accordance with IW-3510, these velves alli be cycled to vertfy operability eac and vented during cold shutdown or refueling.                                                                                               -
re64/611136

i (lW)
Test         Reifef    Testing Valve              Normet Stre Posttfon  Requirements   Requests Alternettve Valve          Class /                                                         Type   Actuation Contafssent isolation                (Inches) geweber_      Category C-           0        M-lW-25      QCS 12           CA        M0 m-lW-26      LLRT 2-51-651         1A    SIS isol.4 ton Valve                                                                      LT PI
                                                                                          -          0           LT       RR-lW-26     LLRT 1/2           CK 2AC  Air Sample Containment isolation 2-AC-54
                                                                                           -         0     -
LT       RR-lW-26     LLRT 1/2            CK 2AC  Air Sample Contaf rument isolation 2-AC-55                                                                                                                                LLRT LC            LT       RR-lW-26 6           BFLY      IWS 2-Flite 108      2AC   Fire Protectfon Containment isolation
                                                                                            -        C            LT       RR-lW-26     LLRT 6           CK 2-F!!!E 109      24C   Fire Protection Containment Isolation re84/611136                                                                                                        .

4 4 Docket No. 50-336 A07351 Attachment 16 Revised Class 2 Isometric Drawings l
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