ML18026A331

Forwards Responses to Questions 123.1 - 123.9 Per 810202 Request for Addl Info.Info Will Be Incorporated Into Next Revision of Facility FSAR

ML18026A331
Person / Time
Site:	Susquehanna
Issue date:	03/17/1981
From:	Curtis N PENNSYLVANIA POWER & LIGHT CO.
To:	Youngblood B Office of Nuclear Reactor Regulation
References
ER-100450, PLA-660, NUDOCS 8103180114
Download: ML18026A331 (29)

Text

r)'EGUL, RY INFORMATION DISTRIBUTI+ SYSTEM (RIDS)

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ACCESSION NBRs8103180110 DOC ~ DATE: 81/03/17 NOTARIZED:

NO DOCKET' FACIL:50 387 Susquehanna Steam Electr)c Station, Un) t li Pennsyl va 05000387 50 388 Susquehanna Steam Electric Station~

Unit 2~ Pennsylva 05000388 AUTH,NAME AUTHOR AFFILIATION CURTIS'

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Pennsylvania Power L Light Co ~

REC IP ~ NAME RECIPIENT AFFILIATION YOUNGBLOODiB.J.

Licensing Branch 1

SUBJECTs. Forwards, responses to questions 123.1 123,9 per 810202'equest for addi info, Info will be incorporated into next revision of facility FSAR ~

DISTRIBUTIoN CODE.:

B001S COPIES RECEIYED:LTR

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PSAR/FSAR AMDTS and Related Correspondence NOTES':Send I8E

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amends, Send ILE 3 copies FSAR 8 all amends."

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INTERNALs ACCID EYAL BR26 CHEM ENG BR 08 CORE PERF BR 10 EMERG PREP 22'EOSCIENCES10 HYD/GEO BR 15 ILEi 06 LIC QUAL BR MECH ENG BR 18 NRC PDR 02 OP LIC BR'ROC/TST REY 20, R

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TWO NORTH NINTH STREET, ALLENTOWN, PA. I 81 01 PHONEr t215) 770-5151 NORMAN W. CURTIS Vice President-Engineering tt Construction-Nuclear 770-5381 March 17, 1981 Sinr, q 7,3,

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3 eoAtAI(33~~70ar Mr. B. J. Youngblood, Chief Licensing Projects Branch 81 Division of Project Management U.S. Nuclear Regulatory Commission Washington, D.C.

20555 SUSQUEHANNA STEAM ELECTRIC STATION RESPONSES TO QUESTIONS 123.1 THRU 123.9 ER 100450 FILE 841-2 PLA-660

Dear Mr. Youngblood:

In response to the February 2,

1981 request for additional information (Tedesco to Curtis), attached please find PP&L's responses to questions 123.1 thru 123.9.

This information will be incorporated into the next revision of the Susquehanna SES FSAR.

N. W. Curtis Vice President-Engineering

& Construction-Nuclear TEG/mks Attachment afoot t/qo PENNSYLVANIA POWER 5L LIGHT COMPANY A

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SSES-FSAR QUESTION 123. 1 Pursuant to General Design Criterion 2, safety-related structures, systems and components are to be'esigned for appropriate load combinations arising from accidents and severe natural phenomena.

With regard to the vibratory loads'attributed to the feedback of hydrodynamic loads from the pressure suppression pool of the containment, the staff requires that safety-related mechanical, electrical, instrumentation and control equipment be designed and qualified to withstand effects of hydrodynamic vibratory loads associated with either safety relief valve (SRV) discharge of LOCA blowdown into the pressure suppression containment combined with the effects of dynamic loads'rising from earthquakes.

The criteria to be used by the staff to determine the acceptability of your equipment qualification program for seismic and dynamic loads are IEEE Std. 344-1975 as supplemented by Regulatory Guides 1.100 and 1.92, and Standard Review Plan Sections 3.9.2 and 3.10.

State the extent to which the equipment in your plant meets these requirements and the above requirements

,to combine seismic and hydrodynamic vibratory loads.

For equipment that, does not meet these requirements provide justification for the use of other criteria.

RESPONSE

I.

BOP For Susquehanna Project, all BOP Safety related mechanical,

'lectrical, instrumentation and control equipment located inside Primary Containment, Reactor and Control buildings, is being qualified for Seismic loads in combination with hydrodynamic vibratory loads associated with SRV discharge and LOCA blowdown.

Although the SRSS

'ethod of combination of seismic and hydrodynamic loads is acceptable, for the project to be conservative, the loads are combined by absolute sum method.

The cases which have deviations from the absolute sum method 'of combination will be identified in the qualification reports.

The criteria for the qualification of BOP equipment for seismic loads is described. in Section 3.7b.3.of the FSAR.

The criteria for load combinations and methodology for the design assessment and qualification of Safety related BOP equipment for seismic and hydrodynamic loads have been.described in Sections 5.7 and 7.1.7 of the Design Assessment Report (DAR). Rev.

2.

Basically the requirements of IEEE Std. 344-1975 as Supplemented by Regulatory guides 1.100 and 1.92 and SRP Sections 3.9.2 and 3.10 are covered in the criteria with the following exception for spatial combination of. three components of dynamic motion as stated in Section 7;1.7.1.3 of the DAR.

The criteria states "the response at any point is the maximum value

SSES-FSAR

, obtained by adding the response due to vertical dynamic load with the larger value of the responses due.to one of the horizontal dynamic loads by the absolute sum method."

All Susquehanna BOP equipment is being qualified for the criteria discussed above.

1I.

NSSS LOAD COMBINATIONS:

These were transmitted to the NRC on 8/28/80 as Page 3 of Attachment N

to PLA-536.

This was in response to NRC Question 110.42.

IMPLEMENTATION OF LOAD COMBINATIONS:

I'he GE SQRT Program uses outputs from,the GE Equipment Adequacy Evaluation Program which combines dynamic loads by SSES as accepted by the NRC in NUREG-0484.

The individual items associated with the load combinations are added as described below:

Steady State Events (e.g.,

Dead Load, Pressure)

- Absolute Sum Time Varying Components (e.g.,

Maximum Seismic, Maximum Hydrodynamic)

SRSS Components of Events (e.g.,

Maximum X-Load Due to Y-Earthquake) - SRSS Modal Response-SRSS, except for closely spaced modes where effects are combined by Absolute Sum, Double Sum, or Grouping.

Details for each item of equipment are contained in that equipment's Design Record File which is available for audit.

123.1-2

SSES-FSAR Provide the fol'lowing information:

(i)

.Two summary equipment lists (one for -NSSS supplied equipment and one for BOP supplied equipment).

These lists should include all safety related mechanical components, electrical, instrumen-

tation, and control equipment, including valve actuators and other appurtenances of active pumps and valves.

In the lists, the following information should be specified for each item of equipment.

(1)

Method of qualification used:

a)

'Analysis of test (indicate the company that prepared the

report, the reference report number and date of the publication).

b) If by test, describe whether it was a single or

~

multi-frequency test and whether input was single axis or multi-axis.

c) If by analysis, describe whether static or dynamic, sing1e or multiple-axis analysis

'was used.

Provide natural frequency (or frequenci'es) of equipment.

(2)

Indicate whether the equipment has met the qualification requirements.

(3)

Indicate the system in which the equipment is located and whether the equipment is required for:

a) hot stand-by b) cold shutdown c) both d) neither (4)

Location of equipment, i.e., building> elevation.

(5)

Availability for inspection (Is the equipment already installed at the plant site?)

123.2-1

SSES-FSAR 4

1 (ii)

An acceptable scenario of how to maintain hot stand-by and cold shutdown based on the following assumptions:

(1)

SSE or'EE (2)

Loss of offsite power (3)

Any single 'failure (iii) A compilation of the required response spectra (RRS) for all applicable vibratory loads (individual and combined if required) for each floor of the nuclear station under consideration.

RESPONSE

The response to this question was submitted via PLA-627 (Curtis to Youngblood) dated February 5,

1981.

123.2-2

SSES-FSAR UESTION 123.3 Identify those"items of nuclear steam supply system and balance-of-plant equipment requiring reevaluation and specify why reevaluation is necessary (i.e. because the original qualification used the single frequency, single

'xis methodology, because equipment is affected by hydrodynamic loads, or

,because both of the above conditions were present). for each item of equipment.

RESPONSE:'

Originally almost all Safety related BOP equipments for Susquehanna had been qualified for only Seismic loads.

This equipment has been re-,evaluated due

'o the inclusion of new hydrodynamic (SRV 6 IOCA) loads, and are being re-qualified with respect to the criteria described in DAR Section 7.17.

The qualification program for the BOP Safety related equipment is being executed in the following four phases.

Phase-I:

uglification of E ui ment for Onl Seismic Loads:

The only known. dynamic load at the time of execution of this 'phase of the program was Seismic loads.'uring this phase, the vendors supplying the.

equipment were required to qualify the equipment in accordance with the requirements specified in FSAR Subsection 3.7b.3.

Phase-II:

Evaluation for Combined Seismic and H drod namic (SRV 6 LOCA) Loads:

This phase was undertaken to evaluate if the existing Seismic qualification of all Safety related BOP equipment could be extended to the combined Seismic and hydrodynamic loads.

The criteria used for the re-evaluation is described in DAR Section 7.1.7.

The general problem areas identified during this evaluation and the proposed action to mitigate these problems are shown below.

123.3-1

SSES-FSAR PROBLEM ACTION'dditional 1lydrodynamic Loads Flexibility of Equipment Support not considered Inadequate Modelling Inadequate Testing o

Retest and/or Reanalysis.

o Modifications to equipment or their Supports if.required.

o Provide response spectre considering support flexi-bility.

o Include Support Conditions during analysis or testing.

o Correct during reanalysis.

o Retest o

Qualification by analysis.

Phase III:

Re uglification'Efforts:

'pecifically, the Problem areas identified in the previous phase are resolved during this phase by taking appropriate actions.

The re-qualification reports demonstrate that the criteria of DAR Section 7.1.7 have been complied with.

Phase IV:

Hodifications to E ui ment or E ui ment Su orts:

Equipment or their Supports needing modifications identified during the regulations efforts of Phase III are executed during. this phase.

The following are NSSS equipment:

SYSTEM HPL 8

'afety Relief"Valve MSIV

'lowElement Recirc.

Pump Motor Gate Valve HCU CRD Valves SLC Storage Tank SLC Accumulator SLC Pump SLC Explosive Valve B21F013 B21F022/F028 B21N051/52/53/54 B31C001 B31F023/31/32 C12D001 C12F009/10/11/12 C41A001 C41A003 C41C001 C41F004 123.3-2

SSES"FSAR RHR Heat Exchanger RHR Pump Flow Orifice Assembly LPCS Pump 8t Motor Flow Orifice Assembly

'MSIV Heater MSIV Blower HPCI Pump HPCI Turbine Flow Orifice Assembly RCIC Pump RCIC Turbine Flow Orifice Assembly

'uel Prep Machine Gen.

Purpose Grapple Dryer 8 Separator Sling Head Strong Back Control Rod Grapple Refueling Platform In Vessel Rack Def. Fuel Storage Cont.

Fuel Storage Vault CONTROL ROOM PANELS E11B001 E11C002 E11N012/N014 E21C001 E21N002 E32B001 E32C001/C002 E41C001 E41C002 E41N007 E510001 E51C002 E51N001 E18E001 F18EOll F19E008 F19E009 F20E002 E21E003 F22E006 F22E009 F22E012 Reactor Core Cooling BB Power Range Monitoring Cabinet RPS Div.

1 and 2 L'og VB RPS Div. 2 and 3 Logical VB NSSS Temperature Recorder VB Feedwater 8 Recirculation Instrument Panel NSSS Process Instrument Panel

~

Div 1 RHR/HPCI Relay VB Div 2 RHR/HPCI Relay VB ADS Ch A Relay VB MSIV Leakage Control Div 2 VB

'HPCI Relay VB RCIC Relay VB Inboard Valve Relay Board Outboard Valve Relay VB Div 1 CS Relay VB Div 2 CS Relay VB.

ADS Ch B Relay VB MSIV Leakage Control Div 1 VB Radiation Monitoring Instrument Panel A

Radiation Monitoring Instrument Panel B

Operating BB H12-P601 H12-P608 H12-P609 H12-F611 H12-P614 H12-P612 H12-P613 H12-P617 H12-P618 H12-P628 H12-P654 H12-P620 H12-P621 H12-P622 H12-P623 H12-P626 H12-P627 H12-P631 H12-P655 H12-P606 H12-P633'12-P680 123.3-3

SSES-FSAR Termination Cabinets Plant Operation Benchboard NUCLEAR BOILER H12-P700 Series H12-P853 Condensing Chamber Condensing Chamber Condensing Chamber Condensing Chamber Condensing Chamber Ccndensing Chamber IOCAL PANELS B21-D002 B21-D004AB B21"D006AD B21-D007AD B21-D008AD B21-D009AD Reactor Mater Clean-Up Reactor Vessel Level and'Pressure (A)

Reactor Vessel Level and Pressure (B)

Recirculation Pump A

Jet Pump B

High Pressure Coolant Injection B

.Reactor Core Isolation Cooling A Residual Heat Removal Channel A

Residual Heat Removal Div. 2 Channel B

Recirculation Pumps Drywell Pressure Local Panel A

Drywell Pressure Local Panel B

Main'team Isolation Valve Ieakage Control Core Spray I,ocal Panel A

Standby Liquid Control Main Steam Flow A/B High Pressure Coolant Injection Leak Det.

'Core Spray Channel B

Main Steam Flow C/D High Pressure Coolant Injection Reactor Core Isolation Cooling Leak Det.

Main Steam Flow A/B Main Steam Flow C/D Main Steam Isolation Valve Leakage Con.

High Pressure Coolant Injection Div.

1 A Reactor Core 'Isolation Cooling Div. 2 B SRM/IRM NUCLEAR BOILER H23"P002 H23-P004 H23-P005 H23-P009 H23-P010 H23-P014 H23-P017 H23-P018 H23-P021 H23"P022 H23"P057 H23-P058 H23-P0,4 Div. 2 H23-P001 H23-P011

'H23-P015 H23-P016 H23-P019 H23-P025 H23-P036 H23-F038 Div. 2 (B)

H23-P041 H23-P042 H23-P073 Div.

1 H23-P034 H23-P037 H23-P030/31/32/33 Temperature Element Temperature Element Temperature Element B21"N004 B21-N010AD B21-N014AD 123.3-4

SSES-FSAR Transmitter Transmitter Transmitter Transmitter Transmitter Transmitter Pressure Switch Temperature Element Temperature Element Vacuum Switch Temperature Element

'Differential Pressure Temperature Element Differential Pressure Level Switch Level Switch Temperature Switch Pressure Transmitter Pressure Indicator

'alve, Guide Tube Miscellaneous Parts

'ressure Switch'ressureSwitch Limit Switch Limit Switch L'evel.Transmitter Temperature Element Differential Pressure Differential'Pressure Differential Pressure Pressure Switch

.Switch Pressure Switch Level Switch Level Switch Temperature Element Temperature Element Flow Indicating Switch

~ Differential Pressure Switch Pressure Switch Flow Heter

'Level Switch Level Switch

~ Level Switch Level Switch Level Switch Temperature Element Temperature Element Temperature Element Temperature Indicator Level Switch Temperature Element B21-N015AD B21-N016AD B21-N017 B21-N056AD B21-N064 B31-N014CD B31-N023AB B31-N024AB C12-N013AD C12"N013EF C41-N003 C41-N004 C41-R003 C51-J004AE C51-5110001 C72-N003AD C72-N005AD C72-N006AD C72-N008AD Ell-N008AB Ell-N009AD Ell-N013 Ell-N015A Ell-N015B Ell"N018 Ell-N021AB Ell-N022AB Ell-N023AB Ell-N024 Ell-N029AD Ell-N030AD Ell-N033AB E21-N003AB E21-N006AB E21-N007AB E32-N006 E41"N002 E41-N003 E14-N014 E41-N015AB E41"N018 E41"N024AB E41"N025AH E41-N028AB thru E41-N030AB E41-R002 E51-N010 E51-N011AB 123.3-5

SSES"FSAR Temperature Temperature Temperature Temperature Temperature Temperature Temperature Temperature Switch Element Element Element Element Indicator Element Element Element E51-N021AB E51-N022AB E51-N023AB E51-N025AD thru E51-N027AD E51-R005 G33-N016AF G33"N022AF G33"N023AF G33-N044A 123.3-6

SSES"FSAR UESTION 123.4:

Describe the methods and criteria used to determine the acceptability of the original equ'ipment qualification to meet the required response spectra of item 2. (iii). - 123.2 (iii).

RESPONSE

I.

BOP For'ases where the original spectra for which an equipment was qualified enveloped the combined Seismic and hydrodynamic load spectra of Item 123.2 (iii), the equipment is considered qualified.

Otherwise (which is true for most cases) the equipment is requalified for the combined spectra to meet the criteria discussed in response to Questions

'123.1.

These criteria are described in Section 7.1.7 of the Design Assessment Report.

II.

NSSS

\\

The methods and criteria used to determine the acceptability of the original equipment qualification may be found in General Electric Company's Proprietary reports:

NEDE-24788, "Seismic Qualification Review Team (SQRT) Technical Approach for Re-Evaluation of BWR 4/5 Equipment";

and NEDE-25250 "Generic Criteria For High-Frequency 'Cutoff of BWR Equipment".

123.4-1

SSES-FSAR r

Describe the methods and criteria used to address the vibration fatique cycle effects on the affected equipment due to required loading conditions.

RESPONSE

BOP As described in Subsection 3.7b.3.2 of FSAR, in general, the design of equipment is not fatigue controlled since the number of 'cycles in an earthquake is low.

4 For combined Seismic and hydrodynamic loads for equipment qualified by

analysis, the fatigue effects are implicitly considered since the stresses due to SRV (which are generally controlling for fatigue) are a small contribution to the overall equipment stresses.

Fatigue effects in BOP equipment qualified by testing are accounted for by repetition of the tests.

Typically tests are done for 5 OBE (or 5 upset conditions, i.e.,

OBE + SRV + IOCA) followed by 1 SSE (or 1 faulted condition, i.e.,

SSE

+ SRV + IOCA) in each of front-to-back/vertical and side-to-side/vertical biaxial configurations.

In

addition, on some selected pieces of equipment, vibratory table testing is carried out for an extended duration of time (such as 30 to

'60 minutes) beyond the combined loading test.

The input motions for

~

the extended duration tests will be such that the generated test response spectra for any segment of the extended duration tests will envelope the SRV spectra.

Furthermore, it will be ascertained that

,the equipment performs its intended function before, during and after the vibratory table tests.

The results of the extended duration tests will be documented in the respective qualification reports.

II.

NSSS Vibration fatigue cycle. effects for NSSS equipment designed to ASME code requirements was reviewed at GE by NRC consultants from Battelle

'Pacific Northwest Laboratories on October 7, 1980.

The consultants stated satisfaction with the GE approach which encompasses

OBE, SRV, thermal and pressure cycles.

Non ASME Code components-qualified by test address the "strong motion" phase of seismic and'SRV dynamic motion sufficient to generate maximum equipment response.

These loads are controlling.

GE testing generally consists of 5 upset and 1 faulted test of 30 seconds each which is about 50/ greater than required 'to address strong motion vibration.

123.5-1

SSES-CESAR Non AStK Code components qualified by analysis generally have not, in the past, had to address'vibration fatigue cycle effects.

In most

cases, such effects are not now part of the qualification record.

123.5"2

SSES-FSAR UESTION 123.6:

g Based on the methods and criteria described in items 4 and 5, provide the results of the review of the original equipment qualification with identification of (1) equipment which has failed to meet the required response spectra and required requalification, and (2) equipment which was found acceptable, together with the necessaiy information to justify the adequacy of the original qualification.

RESPONSE

I.

BOP For cases where the original seismic reports can be.extended to qualify an equipment for combined.seismic and hydrodynamic loads by inspection and subsequent concurrence by vendor, such documents form a part of the qualification package.

The following pieces of equipment bought under the indicated purchase order (P.O.) fa11 into this category:

(1)

Cooling and chilled water pumps (P.O.

ijM-327)

(2)

Expansi'on Tanks and'Air Separator Tanks (P.O.

//M-302)

(3)

Nitrogen Gas Accumulators (P.O..

$/M-156)

The rest of the BOP equipment is being qualified for the criteria described in Section 7.1.7 of the Design Assessment Report.

The qualification reports for this equipment will provide the appropriate documentation.

'II.

NSSS Refer to the Response to Question 123.3 for the list of equipment reevaluated by.GE on the Susquehanna SQRT Program.

All of the equipment listed in qualified to SQRT Criteria with the exception of the following:

B21"F022/F028 B31"F031/F032 C12-.F009/F010 FOll/F012 C41"A003 C41-F004 E32-B001 MSIV Gate Valve CRD Valve'LC Accumulator SLC Explosive Valve MSIV Heater Data required from vendor Operability deflection analysis,.

required Operability deflection analysis required A/E pipe accelerations required A/E pipe accelerations required Test required 123.6-1

SSES-FSAR E41-C002 E51-C002 F22-E006 F22-E009

'12-P608 H23-P030

-P031

-F032

-P033 163C1158 272A8005 272A8006 HPCI Turbine RCIC Turbine Invessel Rack Def.'uel Storage Cont.

Power Range Monitoring Cabinet SRM/IRM Panels Flow Transmitter on H23-P074 Switch on H12-

~ P853 Switch on H12-853 Test required Analysis of lube oil piping required Analysis required Analysis required Test required Test required Test required Test required Test required Information to justify qualification of the equipment selected by the NRC for the Site Audit will be available at the site for'RC inspection.

Information to justify qualification of the remainder of the equipment is available for NRC audit at GE-San Jose.

123.6-2

~

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~

SSES-FSAR Describe procedures and schedule for completion of each item identified in item 6.(1) 123.6 (1) that requires requalification.

RESPONSE

I.

BOP Typically, the qualification program is executed in the following steps.

o Determine Qualification Awards Request Vendor (or Consultant)

Quote Receive and Evaluate Quote Place Purchase Order o

Perform Qualification REview 'Test Proceduie Review Analysis Methodology Begin analysis or Testing o

Final Completion Receive and review Requalification Reports Final Approval of the Report The schedule for the completion of the qualification program is shown in the attached Table 123.7-1.

II.

NSSS The response to Question 123.6 lists the equipment found by GE to require requalification along with"a'tatement defining the work to be performed.

All requalification will be completed on a schedule.

sufficient to permit NRC review prior to fuel load.

123.7-1

'I p

TABLE 123.7-1 Page 1 of 6 SCHEDULE FOR COMPLETION

. OF E UIPliENT REQUALIFICATION SQRT Form No.

E-109-1 E-109-2 E-112 E"117-1 E~ni ment 4 kV Switchgear 4 kV Switchgear Sub-Components ESW 6 RHR Pump Motors 480 V Safe-Guard Load Center Unit Substations No. of Items/

2 Units 12 12 Completion Date 3-13-81 5-15-81

'omplete 3"27-81 E-118 E-119A"1 E-119A"2 E-119A-3 E"119BC E-120-1 E-120-.2 E-121-1 E-121-2 E-135-1 E-135-2 E-136 E-151 480 V Motor Control Centers

'Battery Monitors Battery Fuse Boxes Battery Chargers

'4 Vdc, 125 Vdc 6 250 Vdc Battery Cells 8i Racks 125 Vdc Distribution Panels 24 Vdc Distribution Panels 125 V 6 250 Vdc Load Centers 250 Vdc Control Centers Electrical Penetration (Medium Voltage)

Electrical Penetration (Low Voltage)

AC Instrument Transformers Motor Generator Sets 8~ Control Cabinet 24 20 16 22 16 12 12 32 14 4 Sets 4"17-81 3-27-81 3-27-81 3-27-81 5-29"81 3-20-81 4-10-81 3-27-81 4-10-81 5-15-81 5-15-81 3-27-81 Complete E-152 E-155 J-038A Automatic Transfer Switches Control Switches Field Mounted Electronic Pressure Transmitters 44

'2 Complete 6"15-81 Complete

SORT Form No.

J-03B-1 thru J"03B-14 E~ni ment Panel - Hounted Instruments

/

0 No. of Items/

2 Units 242 Page 2 of 6 Completion Date 4th quarter 1981 J-05A-14,31,33,37, Control Panels 6 Devices 10A 8~ B, 43,47,49, 92,93,95 8i 97 31'-30-81 (panels) 6-'15-81 (devices)

J-05B-1 Remote Shutdown Control Panel 5-30-81 (panels) 6-15-81 (devices)

J-27 Reactor Coolant Pressure Boundary Leak Detection System 2

Complete (panels) 6-15-81 (devices)

J-31 Annubar Flow, Elements Complete J-59-1 thru J-59"10 RTD's 54 5-22-81 J-65-1 thru J-65-4 Control Valves in Nuclear Service 28 3-27-81 J-65B-1 thru J-65B-11 Control Valves in. Nuclear Service 86 3-27-81 J-69-1 8 2 Pilot Solenoid Valves J-70"1 J-70-2 J-92-1 thru

. J-92-5 Pressure Regulating Valves Process Solenoid Valves Excess Flow Check Valves J-69B-1 thru 6

Pilot Solenoid Valves 74 76 238 5-15"81 5-15-81 5-15"81 5-15-81 5-1-81 J-98 Carrier Modulator (Isolator) 6-15-81 M-11

( M"12.

H"22-1 8 2 M-30 (78 forms)

M-30 (6 forms)

M"55 ESW Pumps RHR Suction Water Pumps Reactor Building Cranes Diesel Generator Diesel Generator Reacto'r Vessel Top Head Insulation Support Steel 4 Sets 4 Sets Complete Gomplete 4-3-81 Complete 2-27"81 Complete

e SQRT Form No.

M-58 H-60 H"87" 1 M-87-2 M-90 H-149 M-151 M-156

~Eui ment Diesel Oil Transfer Pumps Buried Diesel Generator Fuel Oil Storage Tanks Containment Hydrogen Recombiners Hydrogen Recombiner Power Supply Fuel Pool Skimmer Surge Tanks Containment Vacuum Relief Valves Suppression Pool Suction Strainers Containment Nitrogen Gas

'Accumulators No. of Items/

2 Units 4

20 32 60 Page 3 of 6 Completion Date Complete 3.-27-81 5-15-81 Complete 4-'27-81 5-22"81 Complete Complete M-159-1 thru M-159-21 Nuclear Safety S Relief Valves 58 5-1-81 M-160AC SRV Discharge Line 6 RHR Relief

'alve F055 Discharge Line Vacuum Breakers 68 5-15-81 M-16.4

'H-192 CRD Vent Valve Platform High Density Spent Fuel Pool Racks 48 Modules Complete Complete M-302 M-307-1 thru H-.307-3 Expansion Tanks 8 Air Separators Centrifugal Fans Complete 3-13-81 H-308-1 Vane Axial Fans, Reactor Building 5-1-81 H-308"2 Vane Axi'al Fans, Diesel Generator Building Complete M-308-3 6 4 M-309-1 thru M-309-4 Vane Axial Fans, ESSW Pumphouse Air Handling Units 12 Complete 4-17"81 M-310 M-315 M-317 M-320-1 Centrifugal Water Chillers Reactor Building Unit Coolers Drywell Unit Coolers Chlorine 'Detectors 24 12 5-22-81 5"29-81 3-27-81 6-15-81

SQRT Form No.

E~ni ment No. of Items/

2 Units Page 4 of 6 Completion Date H-320-2-1A Sr 1B

. M-320-2"2A H-320"3 M-320-4 Flow Switches Flow Switc'hes Level Gauge Pressure Differential Switches M"370-5A 6 5B Temperature Switches M-320-6-2A M-320-6-3A 6 7

M-320-8

'"320-9 M-320"10 M-321.-1 Temperature Switches Temperature Switches Pressure Differential Transmitter Temperature Detector Unit Level Switches

. Standby Gas Treatment System-Housing M-320-6-1A 8~

1B Temperature Switches 28 2'4 4

10 18 6-15-81 6-15-81 6-15-81 6-15-81 6"15-81 6"15-81 6-15-81 6-15-81 6-15"81 6-15-81 6-15"81 2-20-81 M-321-2.

Standby Gas Treatment System-Deluge Drain Valves 5-1-81 H-321-3 Standby Gas Treatment System Control Panels 3-6-81 M-323C-1 M-323C-2 M-325 M-327-1 H-327-2 M-334-1. thru

M-334-5

,1 M-336A H-362 H-365 P"10A-1 Air Flow Monitoring Unit SGTS Exhaust Vent Flow Condition-ing 6 Sampling Probe System.

High Efficiency Ventilation Filters Chilled Water Pump Cooling Water Pump HVAC Control Panels 6 Devices HVAC Dampers SGTS Centrifugal Fans Chilled.Water Relief Valves Motor Operated Gate Valves, 600jj 12

'195 Units 3-13-81 3-13"81 Complete Complete Complete 5-30-81 (panels) 6-15-81 (devices) 5-8-81 Complete 5-1-81 6-15-81

SqRT Form No.

P-10A-2 P-10A-3 E~ui ment Motor Operated Gate Valves, 900jI Hotor Operated Globe Valves, 900jj 8 600j/

No. of Items/

2 Units 15 Page 5 of 6 Completion Date 6-15-81 6.-15-81 P"10B P-11A-1 P-11A-2 Hotor Operated Stop Check Valves, 900 j/

Motor Operated Gate Valves, 900jj 2

" Air Operated Testable Check Valves, 900'-15-81 6-15"81 6-1-81 P-12A-1 P12A-2 P12A"3 P-12A-4 P-12B-1 P-12B-2 "P-12B-3 P-14A P-14B P-15A P15B-1 P-15B-2 P-16A-1

'otor Operated Gate Valves, 150jI Motor Operated Globe Valves, 3008 Motor'perated Gate Valves, 3008 Gear Operated Gate 6 Globe Valves, 3008 Motor Operated Gate

Valves, 1508 6 3008 Air Operated Gate Valves, 1508 Gear Operated Gate

& Globe Valves, 150 j/

Motor Operated Globe Valves, 1500jj Motor Operated Globe Valves, 15008 Motor Operated Globe Valves, 15008 Motor Operated Gate Valves, 1500jI Air Operated Gate Valves, 1500jI Motor Operated Butterfly Valves, 1508 24 20 14 13 18 28 6-15-81 6"15-81 6-15-81 6-1-81 6"15"81 6-1-81 6-1-81 6-15-81 6-15-81 6-15-81 6-i5-81 6-1-81 6"15-81 P16A-2

.Air Operated Butterfly Valves, 1508 6-1-81 P"16A-3 Gear Operated Butterfly Valves, 150 jE 1,2 6-1-8i P,"17A-1 P-17A-2 Motor Operated Gate Valves, 900j/

Motor Operated Globe Valves, 900jI 6-15-81 6-15-81

SQRT Form No.

P-17A-3 P-17A 4 P-17B P-18A P"31A E~ni ment Air Operated Testable Check

Valves, 900i/

Gear Operated Gate Valves 900jj Air Operated Testable Check

Valves, 900/I Gear Operated Gate Valves, 150/j l

Air Operated Butterfly Valves, ISog No. of Items/

2 Units Page 6 of 6 Completion Date 6-1-81 6-1-81 6-1-81 6-1-81 6-1-81

SSES-FSAR UESTION 123.8 Describe plans'.for a confirmatory in-situ impedance test and an in-plant SRV test program or other alternatives to characterize the ability of equipment to accommodate hydrodynamic loading.

RESPONSE

In-Situ tests are being performed for the determination of structural dynamic characteristics of the equipment for in-service condition.

This in-situ information is being used as supporting evidence for (a) validating a mathematical model for qualification by analysis, or (b) simulating the

, in-service condition on the vibratory table tests for qualification by testing.

The results and the usage of in-situ testing will be described in the respective qualification reports, whenever such tests are performed.

All safety related BOP equipment fo Susquehanna project is being qualified for combined seismic and hydrodynamic loads for the criteria described in

.Section 7.1.7 of DAR.

Susquehanna has no plans to perform an in-plant SRV test for equipment. qualifications.per se.

An air'bubble test was conducted in the suppression pool in an attempt to simulate the effects of an SRV air clearing transient load.

The data from this test are being studied in an effort to determine the extent of conservatisms in the analyti'cal prediction of applied hydrodynamic loads.

123. 8-1

SSES-FSAR UESTION 123.9:

g To confirm the extent to which the safety related equipment meets the requirements of General Design Criterion 2, the Seismic Qualification Review Team (SQRT) will conduct a plant site review.

For selected equipment, SQRT will review the combined required response spectra (RRS) or the combined dynamic response, examine the equipment configuration and

mounting, and then determine whether the test or analysis which has been'onducted demonstrates compliance with the RRS if the equipment was qualified by test, or the acceptable analytical criteria if qualified by analysis.

The staff requires that a "Qualification Summary of Equipment" as shown on the attached pages be prepared for each selected piece of equipment and submitted to the staff 'two,weeks prior to the plant site visit.

The applicant should make available at the plant site for SQRT review all the pertinent documents and reports of the qualification for the selected

'quipment.

After the visit, the applicant should be prepared to submit certain selected documents and reports for further staff review.

RESPONSE:

Susquehanna SQRT're-visit information required for the SQRT site review has been submitted for all BOP and NSSS equipment.

"Qualification Summary of Equipment" and the pertinent documents,'eports, vendor prints and all necessary information as required are available for SQRT review.

123.9-1

'Y