ML18003B286

Forwards Addl Info Re post-accident Sampling Sys,Including Rev 0 to Chemistry & Radiochemistry Procedure CRC-826, Post-Accident Sample Chloride Analysis, Per SER License Condition 3 & NUREG-0737,Item II.B.3

ML18003B286
Person / Time
Site:	Harris
Issue date:	05/19/1986
From:	Zimmerman S CAROLINA POWER & LIGHT CO.
To:	Harold Denton Office of Nuclear Reactor Regulation
Shared Package
ML18003B287	List: ML18003B286 ML18003B288 ML18003B289
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-2.B.3, TASK-TM NLS-86-148, NUDOCS 8605270104
Download: ML18003B286 (9)

Text

REQULAT INFORl'tATION DIBTRIBUTIO STEl'1 <RIDS)

'CCESBIQN NBR: 8605270104 DQC. DATE: 86/05/ f 9 NOTAR'I ZED: NO DOCKET FACIL: 50-400 Sheav on Hav v is Nucleav Poeev'lant> Unit 1> Cav.ol ina 05000400 AUTH. MANE AUTHOR AFFILIATION ZINNERNAN> B. R. Cav olivia Polllev'c Light CD.

RECIP. Nhl'1E REC IP I ENT AFF1 LIAT ION DENTON> H. R. Office of Nucleav Reactov Regulation> Div ectov'post 851125

SUBJECT:

Fov'b'av'ds addi info v.e post-accident sampling sos> including Rev 0 to Chemistv g 8r Radiochemistv g Pv oceduv e CRC-826>

"Post-Accident Sample Chlovide Apalgsis>" per SER License Condition 3 5 NUREC-0737> Item II. B. 3.

DISTRIBUTION CODE: B001D COPIES RECEIVED: LTR ENCL SIZE:

TITLE: Licensing Submittal: PSAR/FSAR Amdts Zt Related Cov'v espondence NOTES: Application fov pev mit v enewal filed. 05000400 I

REC P IENT COPIES RECIPIENT COPIES ID CODE/NAl'IE LTTR ENCL ID CODE/NANE LTTR ENCL pNR-A ADTB 1 1 PWR-A EB 1 1 PWR-A EICSB 2 2 PNR-A FOB pWR-A PD2 LA 1 PWR-A PD2 PD 1 BUCKLEY, B 01 2 2 PWR-A PSB 1 pNR-A RBB 1 1 INTERNAL: ADN/LFNB 0 ELD/HDS1 1 0 IE FILE 1 1 IE/DEPER/EPB 36 1 IE/DGAVT/GAB 21 1 NRR BNR ADTB 0 NRR PNR-A ADTS 1 0 NRR PWR-B ADTS 0 NRR ROE. N. L 1 NRR/DHFT/HFIB NRR/DHFT/NTB 1 ILE 04 1 RCN2 3 3 /NIB 0 EXTERNAL: 24X 1 BNL<ANDTB ONLY) f DNB/DBS (AIIDTS) LPDR 03 NRC PDR 02 1 NBIC 05 1 pNL GRUEL. R TOTAL NUNBER QF, COPIES REQUIRED: LTTR 34 ENCL 28

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CNK Carolina Power & Light Company SERIAL: NLS-86-108 MAY 1S 1986 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 POST ACCIDENT SAMPLING SYSTEM

Dear Mr. Denton:

Carolina Power R Light Company hereby submits additional information concerning the Post Accident Sampling System (PASS) at the Shearon Harris Nuclear Power Plant. This information is being submitted in response to Safety Evaluation Report License Condition No. 3 and NUREG-0737 Item II.B.3. The attached information responds to specific questions from your staff concerning the demonstration of the applicability of PASS procedures and instrumentation in the post-accident water chemistry and radiation environment, and retraining of operators on a semiannual basis. In addition, attached is information concerning the accuracy, range, and sensitivity of each of the radionuclide and chemical analyses with copies of the appropriate plant procedures.

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

Yours very truly, gg4frs44~

S. R, IZi merman nager Nuclear Licensing Section

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SRZ/JDK/pgp (3789JDK)

Attachments cc: Mr. B. C. Buckley (NRC) Wells Eddleman Dr. J. Nelson Grace (NRC-RII) Mr. John D. Runkle Mr. G. F. Maxwell (NRC-SHNPP) Dr. Richard D. Wilson

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Mr. Jim Wing(NRC) Mr. G. O. Bright (ASLB)

Mr. Travis Payne (KUDZU) Dr. J. H. Carpenter (ASLB)

Mr. Daniel F. Read (CHANGE/ELP) Mr. J. L. Kelley (ASLB)

Wake County Public Library B~og27og04 860 pDR ADOCH 0 Fro

'g E 411 Fayettevilte Street o P. O. Box 1551 ~ Raleigh, N. C. 27602

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NRC QUESTION 1:

Demonstrate applicability of procedures and instrumentation in the post accident water chemistry and radiation environment, and retraining of operators on semiannual basis.

CPRL RESPONSE:

The boron and chloride analyses methods were tested using the standard test matrix suggested in the NUREG-0737 (II.B.3) clarification guidelines. Although the actual matrix solution used in the plant did not include exposure to gamma radiation, similar methods had been successfully tested by our consultant (NUS Corporation) with exposure to varying amounts of gamma radiation.

The boron analysis is performed using a 1:1000 dilution. A 5 mL aliquot of diluted sample is used. The estimated radiation dose to the fluoroborate selective ion electrode is in the range of tens to hundreds of rads based on a diluted sample radiation level of 30 R/hr at 1 cm two hours after the accident and an exposure time of 15 minutes.

Based on experience with otitpr electrometric probes, such as pH probes, which are stable at cumulative doses up to 10 -10 rads, no significant effect on the accuracy of the boron determination or the operating life time of the probe is anticipated. This evaluation was confirmed by Exxon Nuclear Idaho Company and documented in "Evaluation of GE and SEC Chemical Procedures for Post-Accident Analysis of Reactor Coolant Samples," Exxon Nuclear Idaho Company, November 1981.

Post-accident chloride analysis at SHNPP will be performed by ion chromatography using a 100 p L aliquot of a 1:100 diluted sample. Thus, the total radiation dose from one analysis would be in the range of tens to hundreds of rads based on a sample radiation level of 30 R/hr for a 20 minute analysis. Components in the ion chromatograph receiving this radiation exposure include the following:

Cation resin Anion resin Conductivity cell Transistors Capacitors Wire-wound pots Circuit board No radiation damage is anticipated with resins based on experience throughout the nuclear industry. Resins used in purification system ion exchangers in nuclear plants experience radiation doses orders of magnitude higher than the dose anticipated for the ion chromatograph under accident conditions. Resins are conventionally used to separate various radionuclides under high radiation conditions at Battelle without problems.

Damage occurs after extended exposure; however, the degradation process isglow.

Anion resin will start to degrade at about 10 rads and cation resins at 5 x 10 rads. It is anticipated that electronic components of the type inQuded in the ion chromatot',raph will be resistant to cumulative exposure well above 10 rads.

(3789JDK/pgp)

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Based on the above, the boron methods using fluoroborate ion specific electrode and chloride method using ion chromatograph meet the matrix testing requirements.

CPdcL will retrain the chemistry technicians semiannually. This retraining will consist of retraining approximately half of the technicians quarterly in conjunction with the quarterly operability verification testing of the PASS.

(3789JDK/pgp)

NRC QUESTION 2:

Provide the accuracy, range, and sensitivity for post-accident boron and chloride analyses. Also provide the plant procedures for chemical analyses.

CPRL RESPONSE:

NUS Operating Services Corporation (NUSOSC), consultant, performed matrix testing at SHNPP for boron and chloride analysis. The results indicate that SHNPP procedures for boron (CRC-827) and chloride (CRC-826) meet the NUREG-0737 (II.B.3) requirements regarding accuracy, range, and sensitivity.

The matrix test results are:

Parameter A~ccurac ~Ran e Dilution Boron + 396 at 2.0 ppm 500-6000 ppm 1 to 1000

+ 1096 at 0.5 ppm Chloride + 1.296 at 100 ppb ) 10.0 ppm 1 to 100 Chloride analysis of a diluted sample will be used for initial scoping. More accurate chloride analysis will be performed on an undiluted sample that has been decayed sufficiently to be in conformance with ALARAwithin 30 days.

Copies of SHNPP Procedures CRC-827 and CRC-826 are attached.

(3789 JDK/pgp )

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