ML18018B486

Forwards Responses to Draft SER Open Items Re in-core Exit Thermocouple & Subcooling Instrumentation Sys (NUREG-0737, Item II.F.2) & Release of Particulates & Iodines from Condenser Vacuum Pump Exhaust

ML18018B486
Person / Time
Site:	Harris
Issue date:	11/23/1983
From:	Mcduffie M CAROLINA POWER & LIGHT CO.
To:	Harold Denton Office of Nuclear Reactor Regulation
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-2.F.2, TASK-TM LAP-83-541, NUDOCS 8311300247
Download: ML18018B486 (20)

Text

{{#Wiki_filter:v"'EGULATORY I RMATION DISTRIBUTION SYS (RIDS) ACCESSION NBR.8311300247 DOC ~ DATE: 83/11/23 NOTARIZED: NO DOCKET FACIL:50-400 Shearon Harris Nuclear Power Plant~ Unit ii Carolina 05000400 50-401 Shearon Harris Nuclear Power Planti Unit ?i Carolina 05000401 AUTH,NAME AUTHOR AFFILIATION MCOUFFIE~M,AD Carolina Power 8 Light Co. RECIP ~ NAME RECIPIENT AFFILIATION DKNTONgH ~ RE Office of Nuclear Reactor Regulationr Director

SUBJECT:

For wards responses to draft SER open items t'e in core exit thermocouple 8 subcooling instrumentation sys (NUREG-0737'tem II.F.2) 5 release of particulates L iodines from condenser vacuum pump exhaust, DISTRIBUTION CODE: 8001S COPIES RECEIVED:LTR ENCL SIZE: TITLE: Licensing Submittal: PSAR/FSAR Amdts 8, Related Correspondence NOTES: REC IPIENT IO COOK/NAME NRR/DL/ADL NRR L83 LA INTERNAL'LOw~'981 IE/DEPER/EPB 36 IE/DEQA/QAB 21 NRR/DE/CEB ll NRR/DE/EQB 13 NRR/OE/MEB 18 NRR/DE/SAB 24 NRA/OHFS/HFEB40 NRR/DHFS/PSRB NRR/OSI/AFB 26 NRR/OS I/CPB 10 NRR/DS I/ICS8 16 NRR/DSI/PSB 19 NRR/DSl/RSB 23 RGN2 EXTERNAL: ACRS 41 DMB/DSS (AtlDTS) LPOA 03 NSIC 05 COPIES LTTR ENCL 1 0 1 0 1 0 3 3 1 1 1 2 2 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 3 3 6 6 1 1 i 1 1 RECIPIENT IO COOK/NAME NRR L83 BC BUCKLEYpB 01 IE F ILE IE/OEPER/IRB 35 NRR/DE/AEAB NRR/OF/EHEB NRR/DE/GB 28 NRR/DE/MTEB 17 NRR/OE/SGEB ?5 NRR/DHFS/LQB 32 NRR/DL/SSPB NRR/DSI/ASB NRR/OS I/CS8 09 NRR/DS I/METB 12 NR 0 RAB 22 CG F L 04 /t<IB BNL(AMDTS ONlY) FEMA "REP OIV 39 NRC PDR 02 NTIS COPIES LTTR ENCL 1 0 1 1 1 1 1 0 1 1 2 2 1 1 1 1 1 1 1 0 1 1 1 1 1 1 1 1 1 0 1 1 1 1 1 1 1 TOTAL NUMBER OF COPIES REQUIRED: LTTR 53 ENCL 46

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REGULATORY FORMATION DISTRIBUTION SY'M (RIDS) ACCESSION NBR:8311300247 OOC ~ DATE; 83/11/23 NOTARIZED: NO FACIL:50-400 Shear on Harr is Nuclear Power Plant< Unit 1 r Carolina 50-401 Shearon Harris Nuclear Power Plantr Unit 2i Carolina AUTH'AME AVTHi)R AFFILIATION MCDUFFIE,M~ A ~ Carol ina Power 8, Light Co ~ HECIP ~ NAME RECIP IENl'FFILIATION DENTON<H,R. Office of Nuclear Reactor Regulation~ Director

SUBJECT:

Forwards responses to draft SER open items re in core exit thermocouple & subcooling instrumentation sys (NUHEG 0737'tem II.F,2) b release of particulates 8 iodines from condenser vacuum pump exhaust, DISTRIBUTION CODE: 8001S COPIES RECEIVED:LTR ENCL SIZE': TITLE: Licensing Submittal: PSAR/FSAR Amdts 8, Related CorresPondence NOTES: DOCKET 05000400 05000401 RECIPIENT ID CODE/NAME NRH/DL/ADL NHR LB3 LA INTERNAL: ELV/HDSl 1E/DEPER/EP8 36 IE/OEQA/NAB 21 NRR/DE/CEB 11 NRR/OE/EQB 13 NRH/OE/HEB 18 - NRH/OE/SAB 24 NRH/DHFS/HFEB40 NRH/OHFS/PSRB NRR/OS I/AEB 26 NHH/DSI/CPS 10 NRH/DSI/ICSB lo NRH/DS I/PSB 19 NRR/DS1/RSB 25 RGN2 EXTEHNAL: ACHS 41 DMB/DSS (AMDTS) LPDH 03 NSIC 05 COPIES LTTR ENCL 0 1 0 1 0 3 3 1 l 1 2 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 3 6 6 1 1 1 1 1 RECIPIENT IO CGOE/NAME NRP L83 BC BUCKLEYiB 01 IE F ILE IE/OEPER/IRB 35 NRR/DE/AEAB NRR/OE/E.HEB NHR/DE/GB 28 NRR/DE/MTEB 17 NRR/OE/SGEB 25 NHH/DHFS/LQB 32 NHR/DL/SSPB NRR/DS I/ASB NRR/OS I/CSB 09 NHR/DS I/METB 12 NRR/DS I/RA8 22 REG FILE 04 RM/OD AMI/MI8 BNL(AMDTS ONLY) FEMA REP OI V 39 NHC PDR 02 NTIS COPIES LTTH ENCL 1 0 1 1 1 1 1 0 1 2 2 1 1 1 1 1 1 1 0 1 1 1 1 1 1 1 1 1 1 0 1 1 1 1 1 1 1 1 TOTAL NUMBER OF COPIES REQUIRED: LTTR 53 ENCL 46

CSQE, Carolina Power & Light Company HOV 2 3 1983 SERIAL:

LAP-83-541 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT UNIT NOS. 1 AND 2 DOCKET NOS. 50-400 AND 50-401 DRAFT SAFETY EVALUATION REPORT RESPONSES

Dear Mr. Denton:

Carolina Power & Light Company '(CP&L) hereby transmits one original and forty copies of responses to Shearon Harris Nuclear Power Plant Draft Safety Evaluation Report Open Items. The response numbers are listed on the cover page of the attachment along with the corresponding review branch and reviewer for each response. We will be providing responses to other Open Items in the Draft Safety Evaluation Report shortly. Yours very truly, M. A. McDuffie Senior Vice President Nuclear Generation FXT/lcv (8541FXT) Attachment Cct Mr. B. C. Buckley (NRC) Mr. N. Wagner (NRC) Mr. G. F. Maxwell (NRC-SHNPP) Mr. J. P. O'Reilly (NRC-RII) Mr. Travis Payne (KUDZU) Mr. Daniel F. Read (CHANGE/ELP) Mr. R. P. Gruber (NCUC) Chapel Hill Public Library Hake County Public Library Mr. Wells Eddleman Dr. Phyllis Lotchin Mr. John D. Runkle Dr. Richard D. Wilson Mr. G. 0. Bright (ASLB) Dr. J. H. Carpenter (ASLB) Mr. J. L. Kelley (ASLB) ,.-+~ Fayetteville Street o P. O. Box 1551 o Raleigh, N. C. 27602 83ii300247 83ii23 PDR

• DOCK 05000400

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I

LIST OF OPEN ITEMS REVIEW BRANCH AND REVIEWER CORE PERFORMANCE BRANCH/T~ HUANG OPEN ITEN 31 METEOROLOGICAL & EFFLUENT TREATMENT BRANCH/J. HAYES OPEN ITEM (8541FXTlcv)

J ~ ~ ~ Shearon Harris Nuclear Power Plant Draft SER Open Item 31 Su lemental Information The applicant has been requested to provide an evaluation of the conformance of the incore exit thermocouple and the subcooling instrumentation system with NUREG-0737, Appendix B, "Design and Qualification Criteria for Accident Monitoring Instrumentation." ~Res ense The applicant's previous submittal on the documentation required for NUREG-0737 Item II.F.2 provides a description of the inadequate core cooling instrumentation to be used at Shearon Harris. In particular, the design utilizes a computer based processing system (ERFIS) for primary display of incore exit thermocouple and margin of subcooling data. Although ERFIS is non-Class 1E, it receives qualified pressure and temperature signals through an accessible

isolator, and is powered from a high reliability power source which is battery backed.

ERFIS computes margin of subcooling data which is displayed together with incore exit th'ermocouple temperature on the SPDS CRT located on the MCB. A qualified backup redundant display device is also located in the Control Ro'om which will display qualified incore exit thermocouple temperatures. Qualified RCS pressure information can also be obtained from the indicators on the MCB. In accordance with the provisions of Regulatory Guide 1.97 Revision 3, this allows the operator to confirm displayed subcooling data, when used in conjunction with ASME Steam Tables'. An evaluation of the conformance of the above system with NUREG-0737 Appendix B is made as follows: (1) The instrumentation will be environmentally qualified in accordance with Regulatory Guide 1.89 (NUREG-0588). For the backup

systems, qualification applies to the complete instrument channel from sensor to display.

For the primary ERFIS based system, qualification applies up to and including the isolation devices. The isolators are accessible for maintenance during accident conditions. Seismic qualification of the above environmentally qualified systems will be in accordance with Regulatory Guide 1.100. The instrumentation will continue to read within the required accuracy following a safe shutdown earthquake. The instrument range for which it is qualified meets the range required as noted in the applicant's submittal of Regulatory Guide 1.97 Revision 3. (2) No single failure within the above described instrumentation system will prevent the operator from being presented with information necessary to determine the safety status of the plant and to bring the plant to a safe and maintainable condition following an accident.

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31 Page 2 This can be accomplished since RCS pressure instrumentation has redundant trains and incore exit thermocouple instrumentation has the redundancy (4 thermocouples per train per core quadrant) recommended by NUREG-0737 Item II.F.2. Additional diverse pressure and RCS Loop temperature information is available to supplement the other instrumentation should redundant displays disagree. Redundant channels are electrically independent, energized from station Class 1E power

sources, and are physically separated in accordance with Regulatory Guide 1.75 up to and including any isolation device.

At least one channel can be displayed on a direct indicating or recording device. (3) The incore exit thermocouple and RCS wide range pressure instrumentation is energized from station Class 1E power sources. Instrumentation channel availability will be provided as specified in SHNPP Technical Specifications. (5) (6) The guidance of Regulatory Guides 1.28, 1.30, 1.38, 1.58, 1.64,

1. 74, 1.88,

1. 123,

1. 144 and

1. 146 have been utilized as described in FSAR Section 1.8.

C Display and recording capabilities have been provided consistent with those required in Regulatory Guide 1.97 Revision 3. (7) Refer to (6). (8) Post Accident Monitoring instrumentation is easily identifiable by the use of color coded bezels etc. Isolation devices are utilized to ensure that Class 1E instrumentation channels are not degraded by non-Class 1E channels. (10) Means are available for checking channel operational availability during reactor operation. Servicing, testing, and calibrating programs will be specified to ensure that the necessary level of qualification is maintained during plant operation. (12) Removal of channels from service will be controlled by administrative procedures. (13) Administrative control will determine access to calibration, adjustment, and test points. (14) The monitoring instrumentation has included in its design, consideration for minimizing situations that would be potentially confusing to the operator. (15) The instrumentation has been designed to facilitate the recognition, location, replacement, repair, or adjustment of malfunctioning components or modules.

31 Page 3 (16) Monitoring instrumentation includes incore exit thermocouples which measure temperature immediately above the core, and RCS wide range pressure sensors which monitor RCS system pressure. The margin of subcooling is primarily calculated by the ERFIS. The backup method of calculating margin of subcooling is provided by utilizing the above 1E sensor information (1E Display in the MCR) in conjunction with ASME Steam Tables. (17) The above instrumentation will be utilized during normal operation thus assuring operator familiarity. (18) Periodic testing of the instrument channels will be in accordance with the applicable provisions of Regulatory Guide 1.118 as noted in SHNPP FSAR Section 1.8. (8523COMkjr)

Shearon Harris Nuclear Power Plant Draft SER Open Item Additional Information Provide additional information on the release of particulates and iodines from.the condenser vacuum pump exhaust.

RESPONSE

CP&L has completed the calculations necessary to establish a relationship between the noble gas monitor reading and the amount of released particulates and iodines. The approach intended to be used is as presented below. The isotopic concentrations in the condenser vacuum pump effluent stream have been calculated under tech-spec and normal operating conditions. Assumptions used in this calculation were consistent with the assumptions used in calculating the effluent releases presented in Section 11.3 of the FSAR. As described in Attachment 1 of this memo all isotopic concentrations were normalized to XE-133, as a function of time after shutdown. Particulate and iodine releases are estimated by multiplying the condenser air ejector radiation monitor reading, by the appropriate isotopic composition fractions presented in Table 1 of Attachment 1. The primary isotopic contributors to this reading are XE-133 and KR-85. The particulate and iodine composition fractions vary as a function of time as presented in Figure 1 of Attachment l. After completion of hogging operations the amount of particulates and iodines released shall be estimated by the composition fraction method. This shall provide a conservative estimate of releases. It is expected that under actual operating conditions concentration levels less than those shown in the calculations of Attachment 1 shall apply. The calculation methodology is further explained in Attachment 2. It should be noted that no "clean up" credit is taken for the use of the condensate polishing system. This system would normally be operational prior to initiating hogging operations. (8535NLUccc)

~ ~

ATTACHMENT 1 TABLE 1 Relationship Between Nuclides Normalized to Xe-133 Nuclide ~NQ DBCR 18-da Deca 30-da Deca Kr-85m Kr-85 Kr-88 Xe-133m Xe-133 Xe-135 I-131 I-133 Sr-89 Sr-90 Cs-134 Cs-137

2. 78(-2) 1.54(-3) 4.17(-2) 1 ~ 39(-2) 1.00 5.56(-2) 3.89(-4) s.e3(-4) 9 ~ 17 (-9)

1. 81(-1O) 1.01(-6)

7. 36(-7)

(-) 1 ~ 56(-2) (-)

7. 76(-4) 1.00 (-)

8.33(-4) 9.21(-9) 7'9(-8) 1.81(-9) 1.oo(-s) 7.40(-6) (-)

7. 19(-2)

(-) 1.13(-4) 1.00 (-) 1.38(-3) 5 79(-12) 2 ~ 90(-7) 8.48(-9) 4.62(-S) 3.45(-s) (8535NLUccc)

TABLE 2 Xe-133 Condenser Air Ejector Concentrations ( gX/cc) Normal Op. Coolant Levels Tech Spec Coolant Levels Normal Op. Coolant Levels Tech Spec Coolant Levels ~Nc Deca Normal Flow (30 cfm) Normal Flow Hogging (1260 cfm) Hogging -2.0(-4) -6. 2(-2) -4. 8(-6) -1.5(-3) 18-da Deca Normal Op. Coolant Levels

Hogging Tech Spec Coolant Levels Hogging 4.8(-7) 1.5(-4) (8535NLUccc)

ATTACHMENT 2 CALCULATION METHODOLOGY l. Identify the amount of time passed since shutdown. 2. From Figure 1 of Attachment 1 pick the appropriate composition function values for particulates and iodines. 3. Note the average radiation monitors readings. 4. From Figure 2 Attachment 1 based on Step 1 above identify the expected composition of noble gases XE-133 and Kr-85. 5 ~ Using the radiation monitor calibration reports calculate actual concentrations of XE-133 and Kr-85. (This is important only in the case of a prolonged shutdown greater than 40 days. This step was added to prevent overestimation of releases.) 6. Having calculated the XE-133 concentration multiply it by the composition fractions obtained via Step 2 above. (In the case of a short shutdown less than 40 days it can be assumed that the sole contributor to monitor readings is XE-133, the effect of Kr-85 can be ignored.) 7. Record the estimated valves to permit reported as required by R.G. 1 ~ 21. (8535NLUccc)

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