ML18019A517

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Forwards Addl Info Re Initial Plant Test Program, in Response to 851030 Request.Fsar Section 14.2.7 Will Be Revised in Future FSAR Amend to Provide Justification for Exception to Reg Guide 1.20,Position C.3.1
ML18019A517
Person / Time
Site: Harris Duke Energy icon.png
Issue date: 01/06/1986
From: Zimmerman S
CAROLINA POWER & LIGHT CO.
To: Harold Denton
Office of Nuclear Reactor Regulation
References
RTR-REGGD-01.020, RTR-REGGD-1.020 NLS-85-430, NUDOCS 8601140255
Download: ML18019A517 (41)
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Text

REGULATORY 'FOR<I<ATION DISTRIBUTION SY M (RIDS)

ACCE<SSIOI$ NBR: 8601140255 DQC. DATE: 86/01/06 NOTARIZED: NO DOCKET ¹ FAC II: 50-400 Shearon Harv is Nuclear Power Plant< Unit ii Carolina 05000400 AUTH. NAME AUTH <R AFFILIATION ZIMMERMAN<S, R'av'o 1 ina Power 5 Ligh t Co.

RECIP. NAME 'ECIPIENI AFFILIATION DEWTON< H. R. Qftice of Nuclear Reactor Regulation< Director, (post 851125 SUB JECT: Forwards addi info re initial plant test program< in v'esponse to,851030 request. FSAR Section 14. 2. 7 "will be v evised in future FSAR amend to provide gustification for exception to Reg Guide 1. 20< Position C. 3. i.

DISTRIBUTION CODE: B001D TITLF: Licensing COPIES RECEIVED: LTR Submittal: PSAR/FSAR Amdts 5 i ENCL/ SIZE:

Related Correspondence

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NOTES:

REC IP IEN1 COP IFS REC IP IEN'1 COPIES ID CODE/MME LTTR ENCL ID CODE/NAME LTTR ENCL PWR-A ADTS 1 1 PWR-A PD2 PD 1 PWR-A EB 1 1 PWR-A EICSB 1 FO PLO~A fag 1 PWR-A PD2 LA 1 1 BUCKLEY< B 01 2 2 PS p'Lgp g 'Pa Q 1 1 PWR-A RSB 1 1 INTERNAL: ACRS 41 6 6 ADM/LFMB 1 0 ELD/HDS1 1 0 IE FILE 1 1 IE/DEPER/EPB 36 1 1 IE/DGAVT/GAB 21 1 NRR BWR ADTS 1 0 NRR PWR-A *DTS 1 0 NRR PWR-B ADTS 1 0 NRR ROE< M. L 1 NRR/DHFT/HFIB 1 h! RR /DHFT/MTB 1 R R R 1 0 NRR/DSRO/RRAB 1 1 9 FI 04 RON2 3 3 RtI/DDAMI /MIB 0 EXTER NAL: 24X 1 1 BNL(AMDTS ONLY) 1 1 DIIB/DSS (AMOTS) 1 1 LPDR 03 1 1 NRC PDR 02 1 NSIC 05 1 1 PNL GRUEL< R 1 1 TOTAL NUMBER OF COPIES REGUIRED: LTTR 41 ENCL 34

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SlNK Carolina Power 8 Light Company SERIAL: NLS-85-030 JII,N a6 )986 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT UNIT NO. I - DOCKET NO.50-000 INITIALPLANT TEST PROGRAM

Dear Mr. Denton:

Carolina Power R Light Company hereby submits additional information concerning the Shearon Harris Nuclear Power Plant Initial Plant Test Program. The attached information is submitted in response to an NRC request for additional information transmitted by letter dated October 30, 1985.

If you have any additional questions or require further information, please contact me.

Yours very truly, S . Zi merman anager Nuclear Licensing Section 3HE/ccc (307I3DK)

Attachment cc: Mr. B. C. Buckley (NRC) Mr. Wells Eddleman Mr. G. F. Maxwell (NRC-SHNPP) Mr. 3ohn D. Runkle Dr. 3. Nelson Grace (NRC-RII) Dr. Richard D. Wilson Mr. Travis Payne (KUDZU) Mr. G. O. Bright (ASLB)

Mr. Daniel F. Read (CHANGE/ELP) Dr. 3. H. Carpenter (ASLB)

Wake County Public Library Mr. 3. L. Kelley (ASLB)

Mr. H. A. Cole Sb0ii40255 SbOiOb PDR ADOCK 05000400 A PDR @EH 411 Fayettevilte Street o P. O. Box 1551 o Raleigh, N. C. 27602

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SHEARON HARRIS NUCLEAR POWER PLANT NRC UESTION 600.2 FSAR Subsection 10.2.12.1.69, Reactor Internals Inspection Test Summary, should be reinstated or FSAR Subsection 10.2.7 should be modified to provide technical justification for exception to Regulatory Guide 1.20, Position C.3.1.

RESPONSE

FSAR Section 10.2.7 will be revised in a future FSAR amendment to provide justification for exception to Regulatory Guide 1.20, Position C.3.1. Attached are draft FSAR pages reflecting this change.

(3071 JOK/ccc )

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SHNPP FSAR

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P'4.2.7 CONFORMANCE OF TEST PROGRAMS WITH REGULATORY GUIDES The foLLowing applicable regulatory guides will be used as guidance in development of the initial test program'.

a) Regulatory Guide 1.20, Rev. 2, May, 1976, Com rehensive Vibration 122 Assessment Pro ram for Reactor Internals Durin Prep erationaL and Initial Startu Testin'.

J 22 Re uirements for Cleanin of Fluid S stems and Associated Com onents of Mater-Cooled Nuclear PLants.

c) Regulatory Guide 1.41, Rev. 0, March, 1973, Prep erational Testin of J 22 Redundant On-Site .Electric Power S stems to Verif Pro er Load Grou d) ReguLatory Guide 1.52, Rev. 2, March, 1978, Design, Testin , and Maintenance Criteria for En ineered Safet Feature Atmos here Cleanu S stem Air Filtration and Absor tion Units of Li ht-Water-Cooled Nuclear Power Plants.

e) Regulatory Guide 1.68, Rev. 2, August, 1978, Initial Test Proprams for Water-CooLed Nuclear Power PLants.

f) Regulatory Guide 1.68.2, Rev. 1, July, 1978, Initial Startu Test Pro ram to Demonstrate Remote Shutdown Ca abiLit for Water-CooLed NucLear Power Plants.

g) Regulatory Guide 1.79, Rev. 1, September, 1975, Prep erationaL Testing I 22 of Emer enc Core Coolin S stems for Pressurized Water Reactors with the foll,owing clarifications exceptions:

Re . Position CLarifications/Exce tions C.L.b.(2) The capability to realign valves for recirculation shall be tested for the plant.

Test of a recirculation sump to demonstrate vortex controL, acceptabLe pressure drops across suction Lines and valves, and adequate NPSH will be conducted for the plant by model tests. CP&L wilL verify by appropriate physical. examination and flow demonstration test that recirculation sump suction Lines are not obstructed and that valves are properLy installed.

14.2.7"1 Amendment No. 22

INSERT A (PAGE 10.2.7-1)

Re ulator Position Clarifications/Exce tions C.3.1 CPRL commits to the inspection program of 3.1.3 which shall be done by NSSS vendor after Hot Functional Testing.

NSSS vendor shall use vendor inspection procedure and transmit final data to CPRL for plant storage. No CPRL procedure applies.

(3071JOK/ccc)

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SHEARON HARRIS NUCLEAR POWER PLANT NRC QUESTION 600.5.0.K DSER OI-208 FSAR Subsection 10.2.12.2.32, Steam Turbine-Driven Auxiliary Feedwater Pump Endurance Test, should be modified to test system operability for a two hour period under'simulated loss of all AC power conditions (letter to all Westinghouse Systems OL applicants from D. F. Ross (NRC), dated March 10, 1980). This would include securing any area or component cooling systems which are powered from AC sources.

RESPONSE

Auxiliar Feedwater Desi n The Shearon Harris AFW System consists of three pumps and subsystems. The two motor driven Auxiliary Feedwater Pumps are powered from their respective emergency buses.

In the event of loss of the normal power source, power is supplied by the emergency diesel generators associated with these power buses.

The Steam Driven Auxiliary Feedwater Pump is supplied from two steam generators and taken from the main steam lines upstream of the MSIVs. The Turbine Steam Supply Valves are DC motor operated from redundant vital DC buses. The turbine trip and throttle valve requires solenoid actuation to allow a spring to close it. The power supply for the trip solenoid is 125 V DC, thereby maintaining only DC powered control for the steam driven pump. To allow remote opening of the turbine trip and throttle valve, a DC motor operator is provided. The Auxiliary Feedwater Pump Turbine is equipped with an electronic speed controller powered from a safety grade DC supply. Thus, loss of all AC power will not affect the capability of the Turbine Driven Pump to.supply water to the steam generators.

The Steam Driven Auxiliary Feedwater Pump has a self contained lube oil system with attached shaft driven oil pump and oil cooler supplied from the first stage of the pump, discharging back into the suction of the pump. No AC power is required to operate the Steam Driven Auxiliary Feedwater Pump oil pump.

The Shearon Harris Auxiliary Feedwater Pumps (both steam driven and motor) are located in a large area on the 236 foot elevation of the Reactor Auxiliary Building in which excessive ambient temperatures and humidity will not exceed the design limits for safety related equipment in the area.

Auxiliar Feedwater Testin During Hot Functional Testing, a simulated loss of AC power will be demonstrated. This test will align the lB-SB diesel generator to 6.9 KV Emergency Bus 1B-SB and disable both 6.9 KV Emergency Buses 1A-SA and lB-SB from the grid. Auxiliary Buses lA, 1B, and 1C remain energized through the normal supply grid to allow Reactor Coolant Pump operation (simulated heat source). All non'-essential loads are de-energized.

After the IB-SB Diesel Generator is synchronized to the Emergency Bus 1B-SB, Emergency Bus IA-SA is dropped - disabling Auxiliary Feedwater Motor Driven Pump lA-SA. Auxiliary Feedwater Turbine Driven Pump is brought up using DC control power and Auxiliary'Feedwater Motor Driven Pump lB-SB is de-energized and racked out.

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This test will demonstrate operation of the Auxiliary Feedwater Turbine Driven Pump under adverse lighting and communication conditions (see attached draft FSAR Section 10.2.12.1.83 for Turbine Driven Pump two hour run during simulated loss of on-site power).

After fuel load, the subject abstract on the Auxiliary Feedwater Turbine Driven Pump Endurance Test states that a 08 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> endurance test will be run. The two hour run (Section 5.2.5 of March 10, 1980 D. F. Ross (NRC) letter) will be done during HFT.

FSAR Subsection 10.2.12.2.32 will be modified to include a test method to measure and evaluate environmental (temperature and ambient) conditions around the Auxiliary Feedwater Pump to satisfy the acceptance criteria of 10.2.12.2.32.d.2.

The Harris design allows remote (MCB) operation from DC power supplies only and does not require local operation by operators. As stated in the Auxiliary Feedwater Design, the pumps are located in a large area (i.e., not enclosed in a separate room) and operation will not violate environmental qualification.

(3071JDK/ccc)

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SHHPP FSAR

70. Gross Failed Fuel Detection System Test Summary
71. Essential Services Chilled Water System Test Summary
72. Stud Tensioner Hoist Load Test Summary
73. Polar Crane Test Summary
74. Feedwater Heater Drain, Level, and Bypass Control Systems Test Summary
75. Seismic Instrumentation Test Summary
76. Extraction Steam System Test Summary
77. Primary Sampling System Test Summary
78. Secondary Sampling System Test Summary
79. Loss of Instrument Air Test Summary
80. Containment Building Hot Penetration Testing
81. Simulated Loss of On-Site Power Test Summary
82. AC Distribution System Minimum Operating Voltage Test Summary

$ 3. Wuxgliir< f=rr4a~t~r 7 ur 44~c, 0 R~r Ron Pcs+ Sv~~ary There are certain prerequisites which appLy in general to all preoperational tests. For convenience, these generaL prerequisites are Listed here rather than included in each summary.

GeneraL Prerequisites:

a) Construction is compLete and the system is released Lor testing in accordance with th>> start-up manuaL.

b) Required component testing, instrument calibrations, and system L'Lushing/cleaning are complete.

c) Required eLectricaL power supplies, controL circuits, and instrumentation are operational.

d) Approved fLow diagrams, logic diagrams, wiring diagrams, specifications, and vendors'echnical data are available.

e) , For fLuid systems, hydrostatic tests are. complete.

t ) Communications have been established as required.

14.2.12-4 Amendment No. 23

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10.2.12.1.83 Auxiliary Feedwater Turbine Pump Two Hour Run

1. To demonstrate turbine driven pump and related AFW system operation on loss of all AC power to the AFW system.
2. To document component performance during a two hour run of the AFW system in a recirculation mode.
3. To monitor turbine bearing temperatures on plant computer and to ensure the parameters remain within design specifications.
0. To demonstrate remote control station will control turbine speed range of 2300-0100 RPM.
l. All general prerequisites are met.
2. Condensate Storage Tank level within normal operating limits.
3. Service water system available as back-up to Condensate Storage Tank.
0. Steam available for operation of AFW turbine.
5. Hot Functional Testing in progress.
6. Simulated loss of on-site power test in progress.
c. Test Method
1. Start Turbine Driven Pump from MCB by opening 1MS-70, 1MS-72.
2. Monitor turbine bearing temperatures on plant computer.
3. Monitor pump speed on MCB.
0. Vary pump speed from MCB M/A station.
d. Acce tance Criteria
1. Pump starts from operator initiation signal on MCB.
2. MCB M/A station will vary pump speed over range of 2300 to 0100 RPM.
3. Bearing temperatures on turbine, read on computer, do not exceed 160'F.

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SHEARON HARRIS NUCLEAR POWER PLANT NRC QUESTION 600.5.0.t DSER OI-202 FSAR Subsection 10.2.12.2.26, Natural Circulation Test Summary, should be modified to include monitoring of the depressurization rate resulting from the use of auxiliary spray 1n accordance with the Westinghouse Revised Special Low Power Testing Program as described in the letter from E. P. Rahe (Westinghouse) to H. R. Denton (NRC) dated 3uly 8, 1981.

RESPONSE

In lieu of modifying FSAR Section 10.2.12.2.26, FSAR Section 10.2.12.2.22, Pressurizer Heaters and Spray Valves Capability Test Summary, will be modified to include monitoring of the depressurization rate resulting from the use of auxiliary spray.

Attached are marked-up FSAR pages reflecting this change. These changes will be included in a future FSAR amendment.

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2) The general prerequisites are met-
3) Vary charging floM to alloM a 5 percent. increase in pressurizer level and obtain subcooling data.

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4) Initiate an RCS cooldoun of LOF/hour to 552F and obtain subcooling data.

c) Test Method

1) With the pressurizer spray valves closed, alL heaters are energized, and the time to reach a 2300 psig system pressure is measured end recorded.
2) With all pressurizer heaters de-energized, both spray valves are opened, and the time to reach e 2000 psig system pressure is measured and-~~cord ed .

d)

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1) The pressurizer pressure response, as the heaters are energized,

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is within the alloMable~eenge~graphed in the Westinghouse NSSS Start-up Manual. pt'e5s or ip~fw~'<+c

2) The pressurizer pressure response, as the spray valves open, ls Mithin the allowable Manual. A~~ graphed in the Westinghouse NSSS Start-up 4eprncssu<<m+~ ~te
3) The rate of change of pressurizer pressure with respect to the 23 increase of p'ressurizer. pressure end, RCS temperature change is deter'mined f6r natural circulation datg.

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14.2. 12.2.23 Cross Failed Fuel Detection System Test Summery Test Objective

1) To verify proper operation of the Cross FaiLed FueL Detection System during poMer ascension.

b) Prerequis ites

1) PoMer Level is establ.ished to meet the test requirements-
2) The'general prerequisites are met ~

c) Test Method

1) At steady state po~er levels of 25 and 100 percent, verify that detector H.V. is at the settinp determined during the initial preoperational. setup.
2) 'At e power level 'of 100 percent, set the high alarm to 2 X 10 CPM above the level established by 'the plant chemistry section, to be

~it:hin teclinicaL speci f icat ions.

14.2.12-94 Amendment No. 23

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SHEARON HARRIS NUCLEAR POWER PLANT NRC U EST ION 600.7 FSAR Section 1.8, Regulatory Guide 1.68.3, should be modified to address the exception

'aken to Position C.10 as contained in the letter from M. A. McDuffie (CP&L) to H. R.

Denton (NRC), dated November 15, 1983.

RESPONSE

FSAR Section 1.8, Regulatory Guide 1.68.3 will be modified to address the exception taken to Position C.10 in a future FSAR amendment. Attached is the marked-'up draft FSAR page reflecting this change.

(3071 JOK/ccc )

SHNPP FSAR Regulatory Guide 1.68.3 (REV 0) PREOPERATIONAL TESTING OF INSTRUMENT AND CONTROL AIR SYSTEMS 0 lb o,a4, s

The SHNPP project will comp y with this guide as described in Section 14.2.12 except for Regulatory Position C.ll. Regulatory Position C.ll does not appl to SHNPP because of the design of th Instrument Air System. To overpressurize the system would requ e three failures; therefore, overpressurization is not a credible ailure and applicable testing will not be done.

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<< ~ siy~ifcci~t Pe/'fur 44io~ nor~& ws+~D~c~+ ~i> pvesr~rz Amendment No. 11 1.8-86a SHEARON HARRIS NUCLEAR POWER PLANT ~RC UES N FSAR Section 10.2.12.1, Section 10.2.12.2, Figure 10.2.11-1, and Figure 10.2.11-2 should be modified to include all test summaries contained in FSAR Subsection 10.2.12.

RESPONSE

FSAR Section 10.2.12.1, Section 10.2.12.2, and Figure 10.2.11-2 will be modified to include test summaries contained in FSAR Section 10.2.12 in a future FSAR amendment. No changes to FSAR Figure 10.2.11-1 are necessary. Attached are marked-up draft FSAR pages reflecting these changes.

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14.2.12 INDIVIDUAL TEST DESCRIPTIONS These summaries describe the various tests which are specified as preoperationaL tests and start-up tests in ReguLatory Guide 1.68.

Preoperational tests must be completed before fueL Loading, and start-up tests must be completed after fuel Loading. The scope and titles of these summaries may not in all cases correspond directly to the actuaL test procedures which wiLL be used during the two test programs. Certain test procedures may include more than one test as described in these summaries, and in some cases, tests described in one summary may be covered under more than one procedure.

The overaLL scope and content of the tests described in these summaries wilL be addressed in finaL procedures. It should be noted that aLL system acceptance, tests are designated as preoperational tests, but only those tests Listed in Section 14.2.12.1 must be completed prior to fueL loading. The test program will include those features designed to prevent or mitigate anticipated transients without scram (ATWS) that will be incorporated into the SHNPP design.

4.2.12.1 Prep erational Test Summaries The following is an index of preoperationaL test summaries described in this Section.'

Heat Tracing and Freeze Protection Test Summary

2. Hain, AuxiLiary and Start-Up Transformers Test Summary
3. 6.9 kV Switchgear Test Summary
4. 480 V AC Distribution Test Summary
5. 120 V ESF Uninterruptible AC System Test Summary
6. CLass LE DC System Test Summary
7. Normal Emergency AC/DC Lighting Systems Test Summary Communications System Test Summary
9. Annunciator System Test Summary
10. Reactor Protection System Engineered Safety Features Actuation Logic Test Summary Reactor Protection System Engineered Safety Features Actuation Response Time Test Summary
12. Piping Vibration Test Summary Metal. Impact Monitoring System Test Summary
14. Radiation Monitoring System Test Summary

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Excore Nuclear instrumentation System Test Summary Emergency Diesel Generator Test Summary Amendment No. 23 j4.7.12-1

SHNPP FSAR I ~ jI )

17. Deleted I
18. Fire Protection System Test Summary
19. Normal Service Water Test Summary
20. Emergency Service Water Test Summary
21. Compressed and Instrument Air Systems Test Summary
22. Reactor Coolant System Hydrostatic Test Summary
23. RTD/TC Cross Calibration Test Summary
24. Pressurizer Relief Tank (PRT) Test Summary
25. Safety Injection System Performance Test Summary
26. High-Head Safety Injection System Check Valve Test Summary
27. Safety Injection Accumulator/ Test Summary
28. Residual Heat Removal. System Cold Test Summary
29. Residual Heat Removal System Hot Test Summary
30. Containment Spray System Test Summary
31. Chemical and Volume Control ~~SCold Test Summary
32. Chemical and VoLume Control System Hot Test Summary
33. DeLeted
34. Auxi,liary Feedwater System Test Summary
35. Fuel HandLing E<1uipment System '1'est Summary
36. Fuel Pool. Cooling and CLeanup System-Test Summary n
37. Component Cooling Water System Test Summary
38. Gaseous Waste Processing System Test'ummary
39. SoLid Waste Processing System Test Summary
40. [.iquid Waste Processing System Test Summary
41. Containment Isolation Test Summary 42 ~ Containment Integrated Leak Rate Test and StructuraL Integrity Test Summary 14.2.12-2 Amendment No. 23

0 SHNPP FSAR

43. Reactor Coolant Sy'tem Hot Functional Test Summary 44 Piping Thermal Expansion and Dynamic Effects Test Summary

'5. DcLA'ik tot 4ec~k~~ t 0

46. Deleted b q Amc~<~4 L >
47. Pressurizer Pressure and Level Control Test Summary
48. Deleted ~~c ~&a~ t Qctc+~ It p~c~A Ac~(

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50. Main Steam System Test Summary
51. Feedwater System Test Summary
52. Condensate System Test Summary
53. Turbine Generator Test Summary
54. Circulating Water System Test Summary
55. Condenser Vacuum and Condensate Makeup A

System Test Summary

56. Waste Processing Computer Test Summary
57. Containment Ventilation Test Summary
58. Plant HVAC Test Summary
59. Engineered Safety Features Integrated Test Summary
60. Process Computer Test Summary
61. Boron Recycle Te'st Summary
62. Refueling Mater Storage Tank Test Summary
63. Primary Makeup Mater System Test Summary
64. Rod Control. System Test Summary
65. Passive Safety injection System Check VaLve '1'est Summary
66. Containment Recircul,ation Sump Test Summary
67. Containment Vacuum ReLief Test Summary
68. CombustibLe Gas Control System Test Summary
69. Del.eted Amendment No. 23 14.2.12-3

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SHNPP FSAR

70. Gross Failed Fuel Detection System Test Summary
71. Essential Services Chilled Mater System Test Summary
72. Stud Tensioner Hoist Load Test Summary
73. Polar Crane Test Summary
74. Feedwater Heater Drain, Level, and Bypass Control Systems Test Summary
75. Seismic Instrumentation Test Summary
76. Extraction Steam System Test Summary
77. Primary Sampling System Test Summary
78. Secondary Sampling System Test Summary
79. Loss of Instrument Air Test Summary
80. Containment Building Hot Penetration Testing
81. Simulated Loss of On-Site Power Test Summary
82. AC Distribution System Hinimum Operating Voltage Test Summary g'3 . Py xsh~g Fcckwa+c r Yvrg,pe 2 are certain prerequisites which apply in generaL to all preoperational gyp'here tests. For convenience, these general prerequisites are Listed here rather than included in each summary.

General Prerequisites:

a) Construction is compLete and the system is released for testing in accordance with the start-up manuaL.

b) Required component testing, instrument calibrations, and system LLushing/cleaning are complete.

c) Required electrical power suppLies, controL circuits, and instrumentation are operationaL.

d) Approved flow diagrams, Logic diagrams, wiring diagrams, specifications, and vendors'echnical data are avaiLable.

e) , For fLuid systems, hydrostatic tests are compLete.

Communications have been estabLished as required.

Amendment No. 23

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SHNPP FSAR

1) The general prerequisites are met.
2) Suf ficient uni.t auxiliary loads are operable with which to load the AC distributi.on system.

c) Test hiethod

1) Load the requited AC distribution buses to 30 percent or more of each bus'ormal continuous loading and measure/record the steady state voltage 'and loadi,ng.
2) With the required AC distributi.on buses loaded to 30 percent or more, install recorders on the string of buses that were analyzed by the AE to have the lowest voltage. Separately start a large Class 1E motor and a large non-Class 1E motor and record the voltages and loadings of the resulting transie'nts.
3) Transmi,t the bus voltage and loading data taken i.n steps 1 and 2 above to the AE for evaluation and validation of the AE's analytical techniques and assumptions used in the bus loading analysis program.

d) ~Acre recce Criteria

1) Hone 14.2e12.2 Start-U Test Summari.es The following is an index of start-up test summaries described in this Secti.on:

'iovable Zncore Detector Test Summary Rod Control and Position Indication System Test Summary

3. Rod Drive Hechanism Timing Test Summary Rod Drop Ti.me Heasurement Test Summary
5. Reactor Coolant System Flow Heasurement Test Summary Reactor Coolant System Flow Coastdown Test Summary
7. Calibration of Nuclear Instrumentation Test Summary Rod Control System Test Summary Flux Distribution Measurement Test Summary
10. Core Performance Test Summary 14.2.12-78a Amendment No. 17

SHHPP FSAR

11. Power Coefficient =

Measurement Test Summary

12. Control Rod Reactivity Worth Test Summary
13. 'oron Reactivity Worth Test Summary
14. Automatic Rod Control Test Summary
15. Psuedo Rod Ejection Test Summary
16. Steam Generator Moisture Carryover Test Summary
17. Load Swing Test Summary
18. Large Load Reduction and Generator Trip From 100 Percent Power Test Summary
19. Turbine Trip From 100 Percent Power Test Summary
20. Remote Shutdown Test Summary
21. Loss of Offsite Power Test Summary
22. Pressurizer Heaters and Spray Valves Capability Test Summary

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23. A Failed Fuel Detection Test Summary
24. Pressurizer Continuous Spray Flow 'Verification Test Summary
25. Reactor Coolant System Leakrate Test Summary
26. Natural Circulation Test Summary
27. Hain Steam and Feedwater Systems Test Summary
28. Shield Survey Test Summary
29. Loss of Feedwater Heater{'p) Test Summary
30. Hain Steam Isolation VaLve Test Summary
31. Steam Generator Test for Condensation~Induced Water Hammer

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32. Steam Driven Auxiliary Feed Pump Endurance Test 23
33. RTD Loop Bypass Flow Rate Verification Summary 14.2.12-78b Amendment Wo. 23

9 MONTHS COMMERCIAL OPERATION LOTIPOIYER TEST POWER ASCENSION TIJEL INITIAL IBL TOIE 20% SOIL Etl% 50% . $ 0% 70% 80% 00% 100%

LOAD CRITICALITY REACTOR TRIP SYSTEM BORON REACTIVITYWORTHS ROD DRCP TESTS PSEUDO ROD EJECTION REACTOR COOLANT FLOW TESTS REACTOR COOLANT FLOW COASTDOWN CONTROL ROD DRIVE TEST ROD POSITION INDICATORS MODERATOR TEMP REACTIVITYCOEFFICIENT CONTROL ROD REACTIVITYWORTHS INCORE THERMOCOUPLE CHEMICALTEST FLUX DISTRIBUTION MEASUREMENTS REMOTE SHUTDOWN CALIBRATIONOF NUCLEAR INSTRUMENTATION RADIATIONMONITORING EFFLUENT MONITORING POWER COEFFICIENTS AND POWER DEFECTS MEASUREMENTS LOSS OF OFFSITE POWER NATURJII. C.IRCV cFIT'IOrV TURBINE TRIP CORE PERFORMANCE EVALUATION UNIT LOAD TRANSIENTS RTD FLOW BYPASS VERIFICATION m8 FLLIID S YSTIc'JET S~CnPJDFP<q F:c.410 S/STCmS SHEARON HARRIS NUCLEAR POWER PLANT Carolma Power & Light Compaity FINALSAFETY ANALYSIS REPORT INITIALSTARTUP TEST SCHEDULE-ISHNPPI FIGURE 142.11 2

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SHEARON HARRIS NUCLEAR POV/ER PLANT CIIC I FSAR Appendix A should be modified to address all PSRB requests for additional information.

RESPONSE

FSAR Appendix A will be revised to address all PSRB requests for additional information in a future FSAR amendment.

(3071 JOK/ccc )

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SHEARON HARRIS NUCLEAR POWER PLANT

~+C(CS FSAR Subsection 10.2.12.1.06, Pressurizer Safety Valves Test Summary, should be reinstated or FSAR Subsection 10.2.7 should be modified to provide technical justification for exception to Regulatory Guide 1.68, Appendix A.l.a.(2)(i).

RESPONSE

FSAR Section 10.2.7 will be modified to provide justification for exception to Regulatory Guide 1.68, Appendix A.l.a.(2)(i). Attached is the marked-up draft FSAR page reflecting this change.

(3071JDK/ccc)

SHNPP FSAR

14. 2. 7 CONFORMANCE OF TEST PROGRAMS WITH REGULATORY GUIDES The following applicabLe regulatory guides will be used as guidance in development of the initial test program'.

a) Regulatory Guide 1.20, Rev. 2, May, 1976, Com rehensive Vibration 22 Pro ram for Reactor Internals Durin Prep erationaL and Initial J

Assessment Startu Testin Re uirements for Cleanin of Fluid S stems and Associated Com onents of Mater-Cooled NucLear PLants.

c) Regulatory Guide 1.41, Rev. 0, March, 1973, Prep erational Testin of Redundant On-Site Electric Power S stems to Verif Pro er Load Grou Assi nments.

d) Regulatory Guide 1.52, Rev. 2, March, 1978, Design, Testing, and Maintenance Criteria for En ineered Safet Feature Atmos here Cleanu S stem Air Filtration and Absor tion Units of Li ht-Water-Cooled Nuclear Power PLants.

QIV564~ e) Regulatory Guide 1.68, Rev. 2, August, 1978, Initial. Test Proprams for 1 Water-CooLed NucLear Power PLants.

f) Regulatory Guide 1.68.2, Rev. 1, July, 1978, Initial Startu Test Pro ram to Demonstrate Remote Shutdown Ca abilit for Mater-CooLed NucLear Power Plants.

g) exceptions.'22 Regulatory Guide 1.79, Rev. 1, September, 1975, Preo erational Testin of Emergenc Core Coolin S stems for Pressurized Water Reactors with the following clarifications

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2 Re . Position CLarifications/Exce tions C.L.b.(2) The capability to realign vaLves for recirculation shall be tested for the plant.

Test of a recirculation sump to demonstrate vortex control, acceptable pressure drops across suction Lines and valves, and adequate NPSH wilL be conducted for the plant by model tests. CP&L will verify by appropriate physical examination and fLow demonstration test that, recirculation sump suction Lines are not obstructed and that valves are properly instaLLed.

14.2.7-1 Amendment No. 22

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INSERT I (PAGE 10.2.7-1)

Re ulator Position Clarifications/Exce tions A.l.a.(2)(i) Reactor Coolant System Safety Relief Valves will be vendor tested simulating ambient normal air temperature of, containment and normal loop seal temperature water. The relief valves will be set in place just prior to Hot Functional Testing. No CPRL test to be written (3071 JDK/ccc )

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