Text

Forwards Responses to Electrical Outstanding Issues Described in 840608 Draft Ser.Fsar Changes Described in Responses Intended to Be Incorporated Upon NRC Acceptance
	ML20098E109
Person / Time
Site:	Beaver Valley
Issue date:	09/20/1984
From:	Woolever E; DUQUESNE LIGHT CO.
To:	Knighton G; Office of Nuclear Reactor Regulation
References
	2NRC-4-150, NUDOCS 8409280184
	Download: ML20098E109 (49)
	v • d • e

{{#Wiki_filter:,_ t 'Af Ogg g ~ 2NRC-4-150 "-u---- (412) 787-5141 (412) 923-1960 Nuclear construction Division Telecopy (412) 787-2629 Robinson Plaza. Building 2, Sdte 210 Pittsburgh, PA 15205 September 20, 1984 United States Nuclear Regulatory Commission Washington, DC 20555 ATTENTION: Mr. George W. Knighton, Chief Licensing Branch 3 Office of Nuclear Reactor Regulation

SUBJECT:

Beaver Valley Power Station - Unit No. 2 Docket No. 50-412 PSB Electrical Outstanding Issues Gentlemen: This letter forwstds responses to the issues listed below which were provided by PSB in a draft SER on June 8, 1984. FSAR Changes described in these responses are intended to be incorporated upon acceptance by PSB. The following items are attached: - Attachment 1: Response to Outstanding Issue 182 of the Beaver Valley Power Station Unit No. 2 Draf t Safety Evaluation Report, Section 8.2.2.2. : Response to Outstanding Issue 184 of the Beaver Valley Power Station Unit No. 2 Draft Safety Evaluation Report, Section 8.2.2.5. I : Response to Outstanding Issue 185 of the Beaver Valley Power Station Unit No. 2 Draf t Safety Evaluation Report, Section 8.2.3.1. : Response to Outstanding Issue 187 of the Beaver Valley Power Station Unit No. 2 Draft Safety Evaluation Report, Section 8.3.1.5. : Response to Outstanding Issue 188 of the Beaver Valley Power Station Unit No. 2 Draft Safety Evaluation Report, Section 8.3.1.4 : Response to Outstanding Issue 189 of the Beaver Valley Power Station Unit No. 2 Draft Safety Evaluation Report, Section 8.3.1.6. : Response to Outstanding Issue 190 of the Beaver Valley Power Station Unit No. 2 Draft Safety Evaluation Report, Section 8.3.1.11. : Response to Outstanding Issue 198 of the Beaver Valley Power Station Unit No. 2 Draft Safety Evaluation Report, Section 8.3.3.5. : Response to Outstanding Issue 199 of the Beaver Valley Power Station Unit No. 2 Draf t Safety Evaluation Report, Sections 8.3.3.7.1. o,cp\\ 8409280184 840920 v gDRADOCK05000 g L /

Unitsd States Nuclect Ragulctory Conunicsion Mr. G2orge W. Knighten, Chief Page 2 0: ~ Response to Outstanding Issue 199 of the Beaver Valley Power Station Unit No. 2 Draf t Safety Evaluation Report, Section .8.3.3.7.2. DUQUESNE LIGHT COMPANY By E. (g.' Woo lever Vice President GLB/wjs Attachments Mr. H. R. Denton, Director NRR (w/o attachment) cc: Mr. D. Eisenhut, Director Division of Licensing (w/o attachment) Mr. J. Knox (w/ attachment) Ms. M. Ley, Project Manager (w/ attachment) Mr. E. A. Licitra, Project Managee (w/o attachment) Mr. G. Walton,- NRC Resident Inspector (w/o attachment) COMMONWEAI.TH OF PENNSYLVANIA ) ) SS: COUNTY 0F ALLEGHENY ) On this dd day of ( /// , before me, a r Notary Public in and for said Commonwealth and County, personally appeared E. J. Woolever, who. being duly sworn, deposed and said that. (1) he is Vice Pres ident of Duquesne Light, (2) he is duly authorized to execute and file the foregoing Submittal on behalf of said Company, and (3) the statements set forth in the Submittal-are true and correct to the best of his knowledge. Ot$k _ Y-Notary Public ANITA ELAINE REITER, NOTARY PUBUC ROBINSON TOWNSHIP, ALLEGHENY,COUNJY MY COMMISSION EXPIRES OCTOBER"20,19p6 1-

F-ATTACHMENT 1 Response to Outstanding Issue 182 of the Beaver Valley Power Station Unit No. 2 Draft Safety Evaluation Report Draft SER Section 8.2.2.2: Capability to Reestablish Power from the Of fsite Power System-GDC 17 requires, in part, that each of the of fsite circuits be designed to be available in suf ficient time following a loss of all onsite alter-nating current power. supplies and the other offaite electric power circuit, to assure that specified acceptable fuel design limits and design conditions of the reactor coolant pressure boundary are not exceeded. The description in the FSAR as to compliance with this part of GDC 17 is not sufficient to reach a conclusion of acceptability. By Amendment 3 to the FSAR, the applicant did not provide the requested description. This ' item will be pursued with the applicant and the requests of the staf f review will be reported in a supplement. to this report.

Response

The 138 KV circuit breaker which supplies offsite power to BVPS-2 through System Station Service Transformer (SSST) 2A (TR-2A) is controlled from the Relay House, not from the BVPS-2 main control room. .The 138 KV circuit breaker which supplies of fsite - power to BVPS-2 through SSST 2B (TR-2B), however, is controlled from the main control room. A lockout relay located in the Relay House must be manually reset after. a switchyard bus di f fe rential, prior. to operating the control switch in the. main conrol room to close this breaker. 138 KV circuit total of 5 breaker open/close ope rat ions breaker accumulator.s allow a without recharging. -Refer to the response provided for Question 430.6, Amendment 3. b

w ATTACHMENT 2 2 Response to Outstanding Issue 184 of the ~ Beaver Valley Power Station Unit No. 2 Draft Safety Evaluation Repert Draf t SER Section' 8.2.2.5: :Use'of Automatic. Load Tap Changer

Section 8.3.1.1.1 of the.FSAR indicates that the system station service -

transformer specified with an ~ automatic load tap changer. By 'haendment. 3 to the FSAR,' the applicant, in response to a request for information,. indicated that the automatic load tap changer optimizes voltage on the.4160 volt Class 1E buses for any plant load condition and -. powe r grid voltage variation. The applicant has further implied that the design.is - Class 1E and. meets all the requirements of a Class.IE system. Design-criteria with description and analysis as to the systems compliance with GDC 2, 4, 5,17, and 18 has not been addressed in the FSAR. This ' item will be pursued with the applicant and the results of the staff. review will be reported in a supplement to this report.

Response

System station service transformers TR-2A and TR-2B are non-Class IE transformers that supply of fsite (preferred) power t.o the non-Class 1E 4,160 V~ buses.. The: automatic load tap changing capability of' these Ltransformers optimizes downstream voltages ; at Class IE 4,160 V buse's (2AE and;2DF) when electrically connected to the upstream non-Class 1E buses as' described in Section 8.3.1.1. Although testing - capability is provided.through manual control of the

load tap changer (LTC) and voltage indication in the control room, pe ri-odic tiesting is unnecessary because the LTC's are constantly in service.

-If the LTC does not function properly in automatic, the operator in the is control.- room will be alerted. by voltage indication or alarms and 'can take manual control to restore. voltage to normal before protect ive relaying for the 4KV-.and l emergency buses operates. A preventive main- 'tenance program - based on manufacturer's instructions assures continued ' proper LTC operation. The : frequency of preventive maintenance is based on cycles of operation as monitored by an automatic counting system.

BVPS-2 FSAR MED AUS 91984 mm s transformers, each powered from a different bus of the 138 kV switchyard, reliable offsite power is available to supply BVPS-2 station service and emergency systems. The 138 kV connections between the switchyard buses and the station service transformers are made with overhead lines, with separate towers for each line. The towers for each line are separated such that failure of one tower will. net jeopardize the availability of the redundant circuit. Even with the loss of all but one source of power to the switchyard, sufficient power capacity will still be available for emergency , ' Y ' * '"'_' g N$W Y ) 482~3A) 8.2.1.4 Compliance with Design Criteria and Standards 8.2.1.4.1 Compliance with General Design Criterion 5 g g/ k The 138 kV offsite power circuits are (bared be aaQVPS-1 and) BVPS-2. fin the event of any single compo'iiMiE failm e in tne snarea tion of the circuit, the one offsite power circuit remaining for each unit is capable of powering the engineered safety features (ESF) y equipment required for a design basis accident in one unit and the systems required for an orderly shutdown and cooldg_q _of a he remaining u his complies with General Design Criterion (GDC) 5. 8.2.1.4.2 Compliance with General Design Criterion 17 Two separate, independent circuits are provided between the 138 kV switchyard and the onsite electric distribution system. The circuits are designed and located so as to minimize the likelihood n' their simultaneous failure. Each of the circuits is provided with an independent 138 kV bus, transmission path, and system station service transformer, and supplies one of the two independent redundant load groups of the onsite Class lE power distribution system. This is in l accordance with GDC 17. 8.2.1.4.3 Compliance with General Design Criterion 18 The offsite power system circuitry is designed to permit periodic testing of operability and functional performance of power supplies,

relays, and switches, as described in Section 8.2.1.5, and meets the requirements of GDC 18.

8.2.1.4.4 Compliance with IEEE Standard 308-1974 and Regulatory Guide 1.32 The offsite power

system, described previously, meets the requirements of IEEE standard 308-1974, which stipulates that each preferred power source redundant load group have access to a consisting of one or more power sources.

Furthermore, the design conforms to the preferred design provisions outlined in Regulatory Guide 1.32 in that these circuits are operated with the 138 kV circuit breakers normally closed to provide immediate availability of this source in the event of a loss of onsite power. Amendment 3 8.2-3 October 1983

l NSERT " & " $ h 5:Yrhew S bhir cernee, hransform Trt-2.A and TIL-16, wh'i0- art su.yqo ric) h & \\3 fr ku swdqhyard) are-nrn-Class AG 4ramformari hha.4 Supply offsin (pre Rrrej) peute du 46 hh -Cia.1t 16 4, )60 v 6u;ea, The a.uhrmaAi c. Tod he chans;n$ capa-6;h h of 4%., drAhikrrreo d p&imite_5 doLasiregnv yol4gc3 d C\\ ass 16 4,160 v 6u su (2.AE ani 2.0F) W6 e\\eanalt7 cunnaAcJ b Re ursamn~ nm-cb.ss 16 buses as deste:6d in @Jech B.3. i I. 1 T.B2-3A l 3 i

ATTACHMENT 3 -Response-to Outstanding Issue 185 of the Beaver Valley ~ Power Station Unit No. 2

Draft' Safety Evaluation Report

-Draft SER. Section 8.2.3.1: Capability to Test -Transfer of Power Between Normal'and Preferred Offsite Circuits .The; capability.'to test the trans fer of, power from the normal un it

station service - trans former to the station service transformer has not been specifically addressed in the FSAR.

By Amendment 3 to the FSAR, the applicant, in response to a request for information described the trans fer circuitry, _ haw it is. tested during normal plant operation, = and. its compliance with GDC.18. Based on the 'idescription the ~ staff. concludes that the design is testable, meets the requirements of. GDC 18, ' and is acceptable. It is the staf f's concern, however, thatiperiodic testing of the transfer may create transients in the plant if done during power operation. This concern -will be pursued with the: applicant and the results of the staf f review will be reported

in a1 supplement to this report.

The above description has not been included in Section 8.2~of the FSAR in accordance with the ' guidelines of Regulatory Guide 1.70, Standard Format.and. Content of' Safety Analysis Reports for Nuclear Power Plants. This item will be~ pursued with the applicant and the results.of the ' staff review'will be reported in a supplement to this report. ! Response: A ~ voltage and load ' analysis has been ~ completed for the BVPS-2 system (calculation E-68 entitled " Station Service Voltage and Load Analysis").

Included: in - the calculation is an' analysis of the operation of the normal full plant load (after trans fer) from the normal onsite (unit station service trans formers) power supply' to~ the offsite (system

- station service trans formers) power supply. The calculation indicates ~ satisfactory' operation after the transfer.' Operating-history at BVPS-1 which has = a similar one-line -diagram for this system has shown, that significant transients do not result from -this testing. However, it is expected that this testing at.BVPS-2 will - normally - follow. current practice on BVPS-1 which is to perform - the test during shutdown ~ modes or. the shutdown approach to refueling to further - reduce the -possibility of transients which could adversely af fect power -operations. Section 8.2.1.5 has been revised. to include the. description of the capability. to test. transfer of. power between normal and. preferred offsite. circuits in accordance with our response to Question 430.9 in Amendment-.3.

NOTED AUG 91934 H.Maren BVPS-2 FSAR

8.2.1. 4. 5 ' Compliance with Regulatory Guide 1.47

'} The. surveillance of the.offsite power systen is in accordance with Regulatory Guide:1.47 in that monitoring is provided to indicate the availability of the preferred power source as follows: 1. 138 kV breaker open (annunciated and monitored by the plant computer), and 2. 138 kV bus. voltage level. 8.2.1.4.6 Compliance with Regulatory Guide 1.81 Compliance with Regulatory Guide 1,81 is discussed in Section 1.8. 8.2.1.4.7 Compliance with Regulatory Guide 1.93 As. described in the Technical Specifications, the power operation is initiated and continued without restriction only when the limiting -conditions.for operation are met. If the-limiting conditions for operation.are not met, then' power operation is restricted, as explained by the Technical Specifications. 8.2.1.4.8 Compliance with Branch Technical Position ICSB 11 (PSB) Previous studies have shown that loss of the largest operating unit on che grid (Cheswick or Bruce Mansfield) will not result in loss of grid stability and availability of offsite power. Section 8.2.2.2 provides the results of studies performed to demonstrate stability for BVPS-2 for the most severe cases, which did not include reanalysis for loss of Cheswick or Bruce Mansfield Units. This reanalysis was not necessary since the previous studies showed that loss of either of these units had a negligible effect on BVPS-2. This is, therefore, in compliance with Branch Technical Position ICSB 11'(PSB), Stability of Offsite Power Systems. 8.2.1.S Tests and Inspections The _DLC Procedures and Routine Manual program for testing and inspection of the electrical equipment installation associated with the offsite power meets the intent of GDC 18. These procedures cover periodic testing of protective relays, instrument transformers, power transformers, circuit breakers, and various operating checks to ensure the operability and-functional performance of the components- 'of the system. Transfer of power to the onsite distribution system from the main generator or offsite power system meets the requirements of GDC 18. v [, W. OY fU &C' hMfn 0 JY j Systems Oper(ability Surveillance 8.f7E.6 o 4 -Surveillance information for the preferred power supply system is . displayed in the main control room,-is annunciated, and is monitored t Amendment 3 8.2-4 October 1983

ATTAcameMr ~ Each cf the four nonsafety-related 4,160 V buses has two input supply breakers, one fed from the unit station service transformer, the other fed from the system station service transformer. Tne control circuits for these two supply breakers are interlocked via relay contacts. The opening of one supply breaker will automatically cause the closing of the other supply breaker. The closing will,

however, be blocked'by any of the following:

.i: 1. Overcurrent trip of the closed breaker, 2. Manual trip of the closed breaker, or ./ 3. Loss of voltage at the input of the open breaker. Automatic transfer will be alarmed in the main control room. ' w ire il G E 4/2.- Thetransformay__alsohaccomplishedbyoperatoractuationofatest switch on the 4=m control boarcD. Each of the four buses has two test switches to initiate transfer in each direction. Each 4,160 V bus can be independently transferred. The test switches do not have the capability of overriding the previously stated blocking conditions. At no time during automatic initiated transfer will both supply breakers be closed simultaneously. Plant operators will have the capability of deliberately causing both breakers to be simultaneously closed, thereby paralleling the power supplies. Synchronizing checks built into the control circuits will bicek a paralleling operation if power supplies are not in sync. A forced paralleling fof supplies will be alarmed in the main control room. Since the design of the transfer test switches causes a trip of the closed breaker and the subsequent operation of normal transfer circuitry, this system tests actual operation and is in full fT. compliance with GDC 18. e.2-4-A

w ATTACHMENT 4-Response to Outstanding Issue 187 of the Beaver Valley Power Station Unit No. 2 Draft Safety Evaluation Report 'Draf t' SER Section 8.3.1.5 : Capability of Diesel' to Accept Design Load Af ter Prolonged No Load Operation Section' 6.4.2 of IEEE Standard 6.4.2 of IEEE Standard 387-1977 requires, in part, that the load acceptance test consider the potential ef fects on ~

load f acceptance af ter prolonged no load or light load operation of the diesel generator. The applicant was - requested to provide the results of

~ load acceptance tests or anlaysis that demonstrates :the capability of ^ ! the diesel generator to accept the design accident load sequence af ter prolonged no~-load operation. By Amendment'3 to the FSAR 'the applicant did not provide tha requested test or analysis results. This item will continue to. be pursued with the applicant and the -results will be reported in a supplement to this report.

Response

'A test which demonstrates satisfactory load acceptance following -pro-longed no load

r. light load operation is unnecessary since it would not reflect conditions found' as a result of actual diesel' operating prac -

tices.- As - stated inl the response to question 430.54,. routine testing of: diesels is not performed at less than'25% load. In addition, when the diesels start automatically and cre not required to load (such as initi-ated by a safety injection signal with of fsite: power available) they are ~ normally shutdown upon verifying availability of :of fsite power. Since . testing and automatic starts contribute nearly all of the. diesel run ' time, ;it can be ' concluded that no pore than a few hours of accumulated no ' load or light ' load running wimi occur. Since the ve ndor analysis shows: that~ as. much as.24 hours ofi no ' load operation is ac ceptable, it - would be ' meaningless to perform a test of operating practices 'which are many-hundreds of percent more conservative than the vendor analysis even ~ assuming no conservatism in the vendor analysis. t i s '- b l r 7

m. -ATTACHMENT 5 Response to Outstanding Issue 188 of the [ Beaver Valley Power Station Unit No. 2 Draft Safety Evaluation Report.

3..

IDraft'SER Section 8.3.1.4: Compliance.to BTP-PSB-2 Section 8.3.1.1.15 of - the FSAR describes the surveill. ace ins trument a-tion provided to monitor' the status of the diesel generator. In this regard, the applicant was requested to describe how the Beaver Valley design ' complies with the guidelines of Branch Technical Position PSB-2. - By L hnendment 3 to the FSAR the applicant did not provide the requested -description. This, item ' will.. be. pursued with the applicant and the. results : of - the staff review will be reported in a supplement to this report.

Response

The criteria for ' alarms ~ and indications associated with the diesel generator unit bypassed and inoperable status as described,by Branch . Technical Position PSB-2 for BVPS-2, is as follows: 1. Diesel generator ? mit bypass inoperability status is automatically indicated in the. main control room by a unique annunciator window for each of the - two - redundant diesel generator units. The annunci- + ator windows -indicate." Diesel Generator 2-1 Local Panel Trouble" and " Diesel Genrator 2-2. Tecal Panel TroTble." - Local manually induced indication is not provided in each diesel generator room as automa-tic bypassed and tinoperable status conditions are provided to alert the main' control room for all required diabling functions. 2 '. In ' addition to the unique annunciator windows as described 'above, individual bypassed and inoperable status annunciators are-alsu provided in both the main control room as well a .n ' each diesel generator room. These ' status conditions, as de t,ic t ed in Figures 7.5-28, 7.5-29', and 7.5-30 are on separate windows ' for both electri-cal and mechanical functions that' would preclude each' diesel genera-tor from an automatic. start. Unique local windows indicating " diesel generator-trouble" are not provided for each diesel genera- ' tor, as aufficient local individual windows will provide sufficient: function (s). disabling information. to the operator to perform all required 3. Diesel generator units are not shared on BVPS-2. They are completely l! independent to each other. 4' The indication system is designed and installed such that i t' precludes the possiblity of adverse ef fects on the diesel generator -units. Failure-in the ' indication equipment does not result in . diesel generator unit failure or bypass of the diesel generator unit. .In addition, the bypass indication does not reduce the required independence between the. redundant diesel generator units. 1

_ _ ' 5. The indication. system has a capability of ensuring its operable status during normal plant operation to the extent that. the indicat-ing and annunciating function can be ' verified. This verification is _ provided-by specific computer point indication (main control room) for the. required indication operabil.ity status. {. - 1<v 4-4m+- yr ,y w,-%, -w-w_ym %e--,3=-pgrw -g - m g 9 y y-c --qt g y.- y - m-w g p rm-i w m -w-,.-yWe+T-py r - p t-w p,em re mw yg--Myn-m+w.-,= qe gwe-w--y w = m we

ATTACHMENT 6 ~ Response'to Outstanding Issue-189 of the - Beaver Valley Power Station Unit No. 2 Draft _ Safety Evaluation Report Draf t - SER' Section l 8.3.1.6 : Diesel Generator Loading Above its Continuous ~ ' Rating- 'Section 8.3.1.1.15 'of _ the FSAR states thAt the maximum load imposed on - .the ' diesel generator _ is less than the continuous rating. The continuous. rating has been defined to be 4238 ' KW. In -contradiction, Table 8.3-3 of 'the FSAR states'thatithe worst case loading is 4261 KW, 4261 is greater than' the stated maximum load of 4238 KW imposed. Justification for this contradiction will be pursued with the applicant and the results of the staff-review will be reported in a supplement to this report.

Response

The -4,261' KW worst case total load indicated under the " Safety Injection Signal, Loss of Power, Unit Trip" column on page 9 of Table 8.3-3 in the FSAR cis in error. The sum of the ~ individual ' running loads,'as listed under this column on pages 'l through 9; of the table, is less than 4,261

KW.

The correct totals should be as:follows:

TOTALS:

0-3 minute 4,084 KW 3 minute-1 hour 3,974 KW ~ Greater'than 1 hour 3,974 KW-4,211*KW

Worst Case:

Standby. service' water pump _ motor is only energized if the ~ service water pumps are inoperable. ' The correct. worst + case load summation of 4,211 KW is below the 4,238 KW continuous rating of the emergency, diesel generators. ~ Table 8.3-3 of the FSAR is being amended to indicate the above total. Adequate operator instructions are provided in. normal, test, _and emergency procedures to preclude overloading the diesel generators.

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ATTACHMENT 7 Response to Outstanding Issue 190 of the Beaver Valley Power Station Unit No. 2 3 raft Safety Evaluation Report Draf t SER Section 8.3.1.11: Description of Compliance with IEEE Standard 387-1977-A description as to how the Beaver Valley design complies with the guidelines of IEEE Standard 387-1977 as augmented by Regulatory Guide 1.9 and 1.108 has not been presented in the FSAR nor was the description provided in Amendment 3 to the FSAR as requested. This item will be pursued with the applicant and the results of the staf f review will be reported in a_ supplement-to this report.

~~Response~~
The BVPS-2 diesel generators are in full compliance with IEEE Standard 387-1977, with the exception of the following paragraphs of the above referenced standard: Paragraph 4: Reference Standards (8) IEEE Standard 323-1974, " Standard Criteria for Qualifying Class 1E Equipment for Nuclear Power Generating Stations." The BVPS-2 diesels are qualified utilizing the mild environment concept acknowledged by 10CFR50.49B. (12) IEEE Standard 344-1975, " Recommended Practices for Seismic Qualification of Class IE Equipment for Nuclear Power Generating Stations." The BVPS-2 diesels are seismically qualified in accordance with IEEE Standard 344-1971. Paragraph 5.4: Qualification The BVPS-2 diesels are qualified utilizing the mild environmerit concept adknowledged by 10CFR50.49B. Sect ions 1.8 and 8.3.1.2.1, which describe compliance to Regulatory Guide 1.9, wherein IEEE Standard 387-1977 is refe renced, have be en amended to include the information above. The Load Capability Qualification Test, per Section 6.3.1 of IEEE Standard 387-1977,- paragraphs 1 and 2, will be pe rformed in the field, with loads applied in the order prescribed by Regulatory Guide
~~1. 9,~~
C.14.
o BVPS-2 FSAR f: l TABLE 1.8-1 NOTED AUG 91984 nvarcus USNRC REGULATORY-GUIDES RG No. 1.7, Rev. 2 FSAR Reference Section 6.2.5 CONTROL OF COMBUSTIBLE GAS CONCENTRATIONS IN CONTAINMENT FOLLOWING A LOSS-CF-COOLANT ACCIDENT (NOVEMBER 1978) The design of the hydrogen control system for Beaver Valley -Power Station - Unit 2 follows the guidance of Regulatory Guide 1.7. l RG No. 1.8, Rev. 1-R FSAR Reference Sections 17.5, 13.1, 13.2 PERSONNEL SELECTION AND TRAINING (HAY 1977) Selection and _ training of Beaver Valley Power Station - Unit 2 personnel will follow the guidance of this regulatory guide. RG No. 1.9, Rev. 2 .FSAR Reference Sections 8.3.1, 14.2.12.54, 14.2.12.55 SELECTION, DESIGN, AND QUALIFICATION OF DIESEL-GENERATOR UNITS USED AS STANDBY (ONSITE) ELECTRIC POWER SYSTEMS AT NUCLEAR POWER PLANTS (DECEMBER 1979) Diesel-generator units used as onsite electric power systems at Beaver Valley Power Station - Unit 2 (BVPS-2) have been
~~selected, designed, and qualified following the guidance of this regulatory guide with the following clarifications:~~
f,The diesel generators have been procured in accordance with the 1972_ version of Iratitute of Electrical and Electronics Engineers (IEEE) 's Standard 387. \\ \\ - Seisraic and -environmental qualifi:ation are in accordance with IEEE \\ Standards 344-1971 and IEEE 323-1971, respectively. Refer to the \\ BVPS-2 positions on Regulatory Guides 1.100 and 1.89. lp f( r p l.. ' r p;lh f/f Of e NM g. 3A o# p a c I.s d Amendment 6 3 of 80 April 1984
W NOTED AUG 91984 H.Marcus EVFS-2 FSAR 7 Feriodic testing is. performed on a regularly scheduled basis to -demonstrate the operability and continuity of all Class 1E systems and components. Testing of the onsite Class 1E emergency diesel y generator' units, which will be in accordance with Regulatory Guide 1.108. is addressed in Section 8.3.1.1.15. All periodic testing and inspection will be performed with full inte c ity and availability of the entire Class 1E power systems -in conformance with the bypassed or deliberately inoperable status requirements of Regulatory Guide 1.47. periodic testing and maintenance will be performed for all Class 1E protection systems in conformance with the requirements of Regulatory Guide 1.118. Compliance with Regulatory Guide 1.6 The design 'of the onsite electrical safety-related (Class 1E) power systems is in compliance with Regulatory Guide 1.6. The Class 1E loads for all B7PS-2 voltage levels, that is, 4,160 7 ac, 480 V ac, 120 V ac, and 125 V de, are separated into redundant and completely independent load groups. Manual and automatic interconnections between buses-and loads, interconnections between safety-related (Class IE) and nonsafety-related (non-Class 1E) buses, automatic . loading and stripping of buses, and independence of redundant systems are fully described in Sections 8.3.1.1.4,-8.3.1.1.5, 8.3.1.1.8, and 8.3.1.4, respectively. The 125 V dc Class 1E _ system includes four redundant battery and battery charger combinations, with redundant de load groups specifically assigned to each de bus without automatic connection to any other load group. Each of the two emergency diesel generator units (Section 8.3.1.1.15) is completely redundant, physically and electrically separated relative to the other, and is connected exclusively to its designated 4,160 V ac Class 1E bus. -This design ensures complete independence for the onsite emerg.- ay power sources. Compliance with Reculitory Guide 1.9 The diesel generator units are in compliance with Regulatory Guide Q f,-hg 1.hAsaddressed.nSection 8.3.1.1.15, they have been specified, /M manufactured, and tested to Regulatory Guide 1.9. All-bok #;rg K -designed, f required tests have been performed by the manufacturer with the p f. ' exception of the 2-hour short time /22-hour centinuous rating test df f 1 dAtto'G entitled, Load Capability Qualification (Section C.14 of Regulatory l Guide 1.9). This test will be performed and documented for both te,f[MGRTM(MIh! diesel generetor units when installed. The test procedure is t / described in Section 14.2.12. $ k.. 34 # Q43er-# 8.3-55
INS 6ET '[fh9862MH A ,2 ge/ .~ fgg /s -, (> ~ H ) /, p d1AI e aedrs -kue keen-pxozur_ed Tke y in c small u_cs. wi Vh O_C I&?] V T oh S a f rns+14v+e of Ede&hd_wl end Elecho_Wcs-Fxineers (I EE E)_S_-Igada 4 37x_ed_h fke. eAcepkoa of +L e fo/lo wi j pp s_; p, %19'1$dleEcrix2 % dards f _$EFF &_RL-QT/,_E_kbdCc;j-(;s_fr-f khlgcles IE_spp_med 4 sche Power Gencndin S+diom - % BvPs-2 au 0Gese /1 co-e-a va //Seel Urivi mac., r4 c mics E.ovigoAMEur concur #cGcualdbo6 84 to cFdSO.416-3iTLEEEMin-Mx.hcoG~mn%{ Predices ~ Gr s'eic+1c % li A x d le d oA cla s y Q vipemf & Nuclew Powegegg J;g,. 3kRons - % 8ves-2 Gesels are 9 ei%icnll% 4vnlikh )n a ccor/_sne s _ _ _. _ g v ts m Wl _E L 0 gues-z_(%e,rek ec_f.eRQ;d5 ne OTLl t bl4Co THE M ICb EN V i lled W EM T-P {09CCPT 0-C.k'd Ouj Lfrb GE3 6V 10 (F/SoM 9 8, ~
r ATTACHMENT 8 Response to Outstanding Issue 198 of the Beaver Valley Power Station Unit No. 2 Draft Safety Evaluation Report Draft SER Section 8.3.3.5: Electrical Independence Between Power Supplies ' to Controls Located in Control Room and Remote Locations Section 8.3.1.1.10 of the FSAR indicates that controls for the diesel-generator'and Class 1E circuit breakers are located in the control room and.at ' remote locations. By Amendment 3 to'the FSAR, in response to a request. for information, the applicant indicated that independence of controls between these locations is provided by transfer relays operated by transfer pushbuttons. The details for the. electrical independence between power supplies to these controls will be pursued with the applicant 'and the results of the staff review will'b5 reported in a supplement to this report.
~~Response~~
The controls for the diesel generator and Class IE circuit breakers are fully qualified to all' Class 1E _ requirements in the complete control scheme and related power supplies; i.e., main control room, emergency shutdown. panel, and alternate shutdown locations. The term " independence of controls" between these locations, which is provided by trans fe r relays operated by transfer pushbuttons, was used only in the context that an operator may provide "localis.ed control at -these locations when required. FSAR Section 8.3.1.1.10 will be revised to address the ability to tr ans fer between control stations including reference to safe shut-down capability due to a single exposure fire as described in FSAR Section 9.5.1 and the FPER.'
BVFS-2 FSAR 8.3.1.1.9 Safety-Related Equipment Identification m Each -piece.cf safety-related electrical equipment can be readily identified.by the asterisk that forms part of the identification mark L number. This identification mark number is physically attached to the equipment in a conspicuous location along with a color coded marker that identifies the ossi ned emergency train or channel. 7 Refer:to Section 8.3.1.3 for a description of the equipment numbering system. Cable and raceway identification are also described in Section 8.3.1.3. 8.3.1.1.10 System Instrumentation and Control Remote monitoring of the 4,160 V Class 1E system is provided by bus voltmeters and ammeters located in the main control room. Bus voltmeters are also provided at the emergency shutdown panel (ESP). Each 4,160 V load is provided with a lect 1 ammeter at the switchgear section and a transducer-driven ammeter in the main control room. A control switch, with red and white indicating lights, for each load is mounted on the main control board. A control switch, with red and white indicating lights, for selected 4,160 V loads is also located on the ESP. The red light monitors trip coil continuity and indicates if the circuit breaker is closed and breaker control power is available. The white light is dimly lit when the power circuit is de-energized and monitors availability of control power. A bright l white light indicates an automatic trip of a feeder (or source) circuit. Control switches and indicating lights for 480 V Class 1E incoming supply breakers and feeder breakers (except for HCC feeds) are located on the main control board. Control switches and indicating o lights for selected 480 V loads are also on the ESP. g cph= } Control power for Class.1E equipment is provided as follows: 4,Q.3-12L, Class 1E Equipment Class 1E Control Power Source 4,160 V breaker and associated 125 V de system protective relaying 480 V load center breakers 125 V de system for external 4 protection relaying relaying only. Breaker solid state protective system de-velops its own' trip signals 480 V MCC starters 120 V ac derived from internal centrol transformers Control relays, panels, and 125 V de and 120 V ac vital instrument racks buses Amendment 3 8.3-12 October 1983 L__
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ATTACHMENT 9 Response to Outstanding Issue 199 of the Beaver Valley Power Station Unit No. 2 Draft Safety Evaluation Report Draft SER Section 8.3.3.7.1: ' Description and Analysis of Compliance to GDC 50 In regard to ' electrical containment penetrations, a description as to how the Beaver Valley design meets the requirements of Criterion 50 of Appendix A to 10CFR50, with analysis demonstrating compliance, has not been provided in Section 8 of the FSAR. By haendment 3 to the FSAR, the applicant, in response to a request - for information, provided a description with results of test and analysis to show compliance to GDC 50. Based on this informat ion, the staff considers this item resolved. Documentation of the description and analysis in Section 8.0 of the FSAR will be pursued with the applicant and the results of the staf f review will be reported in a supplement to this report. -Response: A revision to the FSAR (Table 1.8-1 and Section 8.3.1.2.1) has been initiated to indicate compliance to Regulatory Guide 1.6 3, Rev. 2, without exception, w.
BVPS-2 FSAR s TABLE 1.8-1 (Cont)' . Values of 1/2 percent and 1 percent of critical are used for vital piping and components for the 1/2-SSE -and
~~SSE, respectively.~~
In addition, a value of 2 percent of critical is used for reinforced concrete structures for the 1/2-SSE. These values are less than the values given in Table 1 of the regulatory guide and are therefore more conservative. RG No. 1.62. Rev. O FSAR Reference section 7.3.2.2.7 MANUAL INITIATION OF PROTECTIVE ACTIONS (OCTOBER 1973) The design of manual initiation of protective actions at Beaver Unit 2 follows the guidance of this Valley Power Station regulatory guide with the following clarification: Manual initiation of the semi-automatic switchover to recirculation following a LOCA is in general compliance with IEEE 279-1971. However, once safety injection is initiated' manually, all automatic functions follow except for the opening of the containment sump isolation valves. These valves remain closed until receipt of a low level signal from the refueling water storage tank level instrumentation. aod fhe p m
~~d 8#~~
RG No. 1.63, Rev. 2 ~ FSAR Reference section 8.3 ELECTRIC TENETRATION ASSEMBLIES IN CONTAINMENT STRUCTURES FOR LIGHT-WATER COOLED NUCLEAR POWER PLANTS (JULY 1978) Since Beaver. Valley Power Station - Unit 2 (BVPS-2) was docketed g before August 31,
~~1978, the methods described in Regulatory f[~~
~~Guide 1.63 were not required to be used in the evaluation of the BVPS-2 Construction Permit application.~~
~~However, the design _ and p~~
i .g 'f g construction of_ the electric penetration assemblies En VPS-2 N m e c/.'c4NM C g,//sw,nsj chri 4this regulatory guidef r,i Ph f), h-m i A . g lg ~ \\\\ Q RG No. 1.64, Rev. 2 '/ FSAR Reference Section 17.2 QUALITY ASSURANCE REQUIREMENTS FOR THE DESIGN OF NUCLEAR POWER PLANTS (JUNE 1976) Quality Assurance Programs in effect at the time of systems design were followed in the design of BVPS-2 and meet the intent of Regulatory Guide 1.64 with the following clarifications and alternative: Amendment 3 33 of 80 October 1983
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p EVPS-2 FSAR. Ocmpliance with Regulatory Guide 1.32 The design.of the safety-related (Class 1E) power systems is in compliance with Regulatory Guide 1.32. 'Two immediate access circuits are provided for the preferred (offsite) power sources from the transmission network. Each circuit is electrically connected and energized from the common switchyard and available at all times. Each ' battery charger that supplies Class IE 125 V dc systems is designed with full capacity and capability to supply the largest concined-demands of the various steady state
loads, while simultaneously providing sufficient power for adequate charging capacity to its designated battery from its minimum voltage level of 110 V de. irrespective of the BVPS-2 status during which these demands occur.
Test methods, procedures, and intervals for all Class 1E battery performance discharge and service test will be in compliance with IEEE Standard 450-1975. -Independence of redundant standby sources is addressed in Sections 8.3.1.2.1 and 8.3.1.1.15. Ocnnection of non-Class 1E equipment to Class 1E systems is addressed in Sections 8.3.1.1.5, 8.3.1.1.15, and 8.3.1.2.1. . Selection of diesel generator set capacity for emergency power supply, is addressed in Section 8.3.1.1.15. Compliance with Regulatory Guide 1.63 s_ fach containment electrical penetration is rotected for loss of mechanical integrity for all possible value of current which can flow through the penetration conductorm. This includes all possible values of overload and short circuit currents. Where values of overload and short circuit currents are calculated or determined to fall within the thermal limits of the penetration ) conduc to r3), the Gasctors argdeemed to oe seJf-prote,cting. JO &n L.Yr4 TION I.S Where overload and short circuit currents are in excess of the thermal capability of a penetration conductor, two overcurrent protective devices (primary and backup) are provided. These devices provide reliable protection given a single random failure of one of these protective devices. These devices consist of existing protection devices or additional devices when necessary, are qualified for their intended purpose, and are mechanically and electrically independent with the exception of the 4.160 V residual heat removal motor circuits, which require the same de control power source. 3 Gl /k.
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ATTACHMENT 10 Response to Outstanding Issue 199 of the Beaver Valley Power Station Unit No. 2 Draft Safety Evaluation Report Draft SER Section 8.3.3.7.2: Compliance with RG 1.63 Section 8.3.1.2.1'of the FSAR indicates that primary and backup contain-ment electrical penetration protection is provided only where the available fault-current exceeds the current-carrying capabilities of penetration conductors. This design for containment electrical penetra-tion does not meet the guidelines of pos ition 1 of Regulatory Guide 1.63. Position 1 requires primary and backup protection where maximum available fault-current exceeds the current-carrying capability of the penetration versus capability of the conductors. By Amendment 3 t o. the Ft' AR, the applicant indicated that the Beaver Valley design provides prinary. and backup protection as required by RG 1.63 and that the following additional information would be provided by March 1984: a. fault-current versus time curve _ for each representative type cr51e conductor which penetrates primary containment b. test report which verify the capability of penetration to withstand the tot al range of. time versus fault current for worst case environmental conditions Revision to the FSAR to indicate compliance to RG 1.63 without exception and review of the above additional information will be pursued with the applicant. The results of the staff review will be reported in a supplement to this report.
~~Response~~
Attached is the following additional information as requested: 'a. fault-current versus time curves for each representative type cable conductor which penetrates primary containment b. test report excerpts which verify the capability of penetrations to withstand the total range of time versus fault current for worst case environmental conditions
run i n s 7 up& Excer/>f S/1 / ci t ce 'n3 7 as introduced. The copper bar was then placed between secondary mod es 4 and 9 connecting together module assemblies 2-4 nd 6-9. P rima ry dules 2 and 6 were connected to the cur nt source and the overload rrent applied. By this met d, module assemblies j 11-8 and 2-4 were jected to one 9 to two Rated Short-Time k Overload Current Tests. - he cable Jacket temperature of 6-9 was /h a&*. =. - - - -. -
19 dQ The computer print-out and wave forms are included in Figures SA through 208. NOTE 1: The BF readings are the bolted fault current available to the wire sizes following in the table. NOTE 2: The first attempt at shooting the 350 KCHIL triad resulted in the fusing of the external terminals on two phases at the module-power supply interface after 14.5 cycles. These terminals are rated for 250 KCMll and 350 KCMIL use. See Figure 3 The second 350 KCHIL shot was run 10 minutes after the first. The two shots coupled with the inboard DBE temperature was sufficient to cause -2 a leak (20 x 10 Std-cc/sec) between the inboard side and the monitoring volume. The leak, however, is not a through leak. l NOTE 3 AND 4: One wire was blown out at the external connection after 6.5 cycles. f] The shot was repeated. The same wire was again blown out at this same connection after 5 cycles. Sufficient time was allowed between the three 250 KCHIL shots such that the excessive temperature that developed in the case of the 350 KCHIL test was not repeated. 7 p Figure 4 is a picture of the inboard end of S/N 261 after testing. The heating tape has been removed. l 4.2.2 Gas Leak Rate and Pneumatic Pressure Test There was no through leakage detected during or following the Rated Maximum Duration of Rated Short Circuit current Test. Using the techniques described in 4.1.2, detectability is orders of 2 magnitude greater than the required I x 10 Std-cc/sec limit. /DD-N-0 L 1 l'
l 5.0 CONCI.US10N The results of this test in conjunction with the results of'the tests recorded in PEN-TR-77-59 confirm that the prototype penetrations meet the requirements of IEEE Standard 317-1976 and Standard 323-1974. This design can, therefore, be classified as I-electrical. The ratings determined by this test can be used to match the circuit overload protection system as required by Reg. Guide 1.63 - October 1973. W e O l e 9 'O ? ADD PeV-h Q v -r-- e -,-L-

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ML20098E109

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