ML17297B426

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Responds to 820108 Request for Addl Info on TMI Action Item II.F.1 Re Addl Accident Monitoring Instrumentation.Noble Gas & Plant Effluent Sampling & Analysis Discussed
ML17297B426
Person / Time
Site: Palo Verde  Arizona Public Service icon.png
Issue date: 04/06/1982
From: Van Brunt E, Vanbrunt E
ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR
To: Tedesco R
Office of Nuclear Reactor Regulation
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-2.F.1, TASK-TM ANPP-20626-ACR, NUDOCS 8204160284
Download: ML17297B426 (10)


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<<REGULATO INFORMATION DISTRIBUTION TEM QRIDS)

'AGC'ESS ION NBR '8204160284, DOC ~ DATE t l82/04/06 NO TARI'ZED!, YES DOCKET FACIL STN..50:528 >Palo Verde Nuclear -Stat)one 'Unfit

'STN.50 529 'Pa]o Ver de Nuclear,. Statfoni 'Uni~t >>2r 'Ar' zony 'pub 1'f ir 'Ar3zona "Publ f 05000526 05000529

'STN 50-530 ~Palo Vende Nuclear Stationi Unfit r3 ~ A r f zona 'Pub 1-f 05000530

'AUTH ~ NAME eAUQ)OR 'AFFILIATION VANBRUNT'jEi'E. Ar'fzona iPublfc'Senyfce Co.

<<RECIP ~ NAME," RECIPlENT>>.AFFIL1ATION, TEOESCOg'R ~ l ~ 'Assistant .Dfneetor;.for eLfcensi ng SUBJECT! Repppnds..';to,820108 >>request

'II.F.i,re'addi accident monfifoi.',fog f or. addi "f.n go on ~TMIAction Item

-inst>reumentatfon Noble gas 8,plan't>> effluent ~sampl fng '8 .analysis ~dfscUssed.

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OISTRiBUTION CODE'. BQO1S iCOPIES RECEiVED',LjR., <:iENCL SiZE;.- '-<-'~.

TITLEs PSAR/FSAR 'AMDTS and 'Rel ated >Corr espondenoe NOTES: Stander d) zed ip ant ~

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  • sslosess sstlssssess eoezsoeses STA. P.O. BOX 21666 - PHOENIX, ARIZONA 85036 April 6, 1982 ANPP-20626 ACR/WFQ Mr. R.L. Tedesco Assistant Director of Licensing Division of Licensing ~ECBQF@

Office of Nuclear Reactor Regulation APR 15 1982~

U.S. Nuclear Regulatory Commission Washington, D.C. 20555 PS IeeIg ggg~ ~~

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Subject:

Palo Verde Nuclear Generating Station (PVNGS) Units 1, 2 and 3 Docket Nos. STN-50-528/529/530 File: 82-056-026; G.1.10

References:

Letter from F. Miraglia, NRC, to E. E. Van Brunt, Jr.

dated January 8, 1982, subject: Request for Additional Information (PVNGS)

(2) Safety Evaluation Report related to the operation of Palo Verde Nuclear Generating Station (PVNGS) Units 1, 2 and 3, dated November, 1981 (3) Letter from E. E. Van Brunt, Jr., APS, to R. L. Tedesco (ANPP-20157 SlfA/WFQ), dated February 11, 1982

Dear Mr. Tedesco:

The following information is provided in response to Reference 1 regarding II.F.l, attachments 1 and 2;.in clarification o'.=.Reference, 2.

II.F.l Attachment 1 Noble as (a) Background correction for instrument readings, if required.

(b) Location of area monitors relative to the steam dump and relief valves and the procedures for correcting for the low energy gamma emitters indicated by the area monitors.

~Res oese:

(a) The supplied monitors are capable of determining background in their vicinity through a controlled series of commands from the monitor's microcomputer. These commands involve the following:

a) isolate HVAC input to the monitor.

b) flush monitor with nonradioactive purge gas.

c) observe reading and input this as the new background level in the microcomputer.

d) return HVAC input to the monitor. Background is automatically accounted for in displayed results.

f'2oiii02N 82oioh~ PIIu(

PDR ADOC5,05000528..."...

w Mr. R. L. Tedes April 6, 1982 .

ANPP-20626 ACR/WFQ Page 2 (b) The area monitors are located on each steam line approximately one foot upstream of the atmosphere dump valves in the Main Stream Support Structure (MSSS) . Refer to FSAR Figure 12.3-2.

A procedure has been developed to correlate the dose rate at the steam line radiation monitors to the concentration of radionuclides inside the steam piping.

Special consideration has been given to the pipe wall shielding effects upon the low energy portions of the decay gamma flux.

Transport theory shielding calculations were performed using the computer program ANISN. Source term distribution (relative per-centages) is considered consistent with TID 14844.

The resultant calibration curve, as well as the mathematical bases, is contained in the PVNGS Emergency Plan. Refer to Nomograph N4 and Appendix C of the Emergency Plan for further details on the calibra-tion procedure.

NRC uestion:

II.F.l Attachment '2 "-'am lin and Anal sis of Plant Effluents Conformance with the required design basis shielding envelope for the sampling media (this includes the particulate filter also), stated in Table II.R.1-2,(page II.F.1-9) of NUREG-, 0737, should be explicitly spelled out.

The design of the fours lead shields of the sampling media allows for removal and transport to the'nsite analysis'enter without exceeding the criteria of GDC 19 of 5 REM whole body and 75 REM to the extremities.

The specific detail's of the samplers and the removal method are provided in the following paragraphs:

The particulate and iodine collector consists of the following assemblies:

The collector assembly is located within a shielded sampler in order to protect personnel from high radiation level exposure during operation.

This sampler is comprised of a drawer to house the "collector assembly and a lead shield.

The shield is a 3-inch fours lead design with all wetted surfaces constructed from type 316 stainless steel. The drawer assembly is attached and sealed to the shield so that the particulate filter and iodine cartridge are held in a horizontal position. The sample air flows downward through the shield and into this collecting assembly. (Refer to FSAR Section 11.5.2.1.1.7.2)

Mounted directly above the collector is a G.M. detector which measures the radiation buildup level of the collectors. Since the primary function of this detector is personnel protection, the adjustable alarm is set for the maximum acceptable level to ensure the safety of the personnel removing the

0 f la Mr. R. L. Tedesco April 6, 1982 ANPP-20626 ACR/WFQ Page 3 filters for laboratory analysis. When the detector sensing circuit reaches the specified high alarm set point, the associated microcomputer transfers the flow to the next particulate "and iodine assembly, isolates the alarmed assembly, and indicates to the operator the need to replace the collector assembly.

The drawer housing the collector assembly is attached and sealed to the lead shield by the use of a quick release hand-operated latch. This latch is permanently attached to the drawer assembly. The drawer assembly slides out into a shelf eliminating the need to lift the lead-filled drawer when replacing the particulate filter. Once the drawer has been opened, the collector assembly can be removed immediately and placed into the supplied portable 3-inch lead shield for transporting the collectors to the laboratory for analysis.

We believe this information adequately responds to the information request discussed in Reference 1, item 3 (II.F.1., Attachments 1 and 2) and of Reference 2, i.tems II.F.l.l (page 22-27) and II.F.1.2 (pages 22-27, 22-28) .

Please contact me if you have any further questions.

Very truly yours GU~

E. E. Van Brunt, Jr.

APS Vice President Nuclear Projects ANPP Project Director EEVBJr'/WFQ'/de Attachments cc: P. Hourihan R. L. Greenfield A. C. Gehr E. Licitra

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STATE OF ARZZONA )

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COUNTY OF >fARXCOPA)

I,'dwin E. Van Brunt, Jr., xepresent'hat X,am Vice President Nuclear Projects of Arizona Public Service Company, that the foregoing document has been signed by me on behalf of Axizona Public Service Company with full authority so to do, that I have read such document and know its contents, and that to the best of my knowledge and belief, the statements made therein are true.

Edwin E.. Van Brunt, Jr.

Sworn to befoxe me this '8 day of , 198?.

Notary Public Hy Commission expires:

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