ML20214G688

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Advises That FSAR Chapter 12 Acceptable for Review.Request for Addl Info Encl
ML20214G688
Person / Time
Site: Columbia 
Issue date: 04/14/1977
From: Kreger W
Office of Nuclear Reactor Regulation
To: Varga S
Office of Nuclear Reactor Regulation
References
CON-WNP-0165, CON-WNP-165 NUDOCS 8605220403
Download: ML20214G688 (5)
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Text

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DISTRIBUTI0h:

DOCKET FILE N0. 50-397

.NRR READING RAB READING APR 14 1977 DSE READING WEKREGER Docket No.t 50-397 MEMORANDtM FOR:

5. Yarga Chief. Light Water Reactors Branch #4, DPM FRON:

W. Kruger, Chief Radiological Assessment Branch, DSE StBJECT:

ACCEPTANCE REVIEW FOR WPPSS 2 PLANT NAME: WPPSS Nuclear Project No. 2 LICENSING STAGE: OL DOCKET NUMBER: 50-397 MILESTONE NUMBER / BRANCH CODE 01-33 PROJECT MANAGER 3 M. Lynch RESPONSIBLE BRANCH: LWR-4 REQUESTED COMPLETION DATE: 4/15/77 DESCRIPTION OF RESPONSE : Acceptance with requests for infomation REVIEW STATUS: Acceptance Review Complete The radiation Protection Section of the Radiological Assessment Branch has reviewed Chapter 12 and information referenced in Chapter 12 of the WPPSS 2 FSAR..The FSAR provides sufficient information for us to begin our review. However, since the proposed technical specifications are not provided, we can not begin our review of the technical specifications.

We have attached requests for infornation which is not provided in the

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FSAR but is called for by Regulatory Guide 1.70. Revision 2.

This review was performed by R. Each, RPS/RA8 Original signed by W. E. Kresse William E. Kreger. Chief Radiological Assessment Branch l

Division of Site Safety and Environmental Analysis

Enclosure:

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PDR ADOCK 00000397 A

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331.0 M0 LOGICAL H5E PE.'lT 331.1 Describe ho.i information from operating BWR experience is (12.1.3) included in the development of the radiation orotection proceduces.

Section 12.1.2 on design considerations sJacifically describes por.slucioa a' EUR o;aciting e.ge fenc2 inn th+. W:

design.

iiewevar, Sectico 12.1.3' co4s not describe he.v v.a operating experience is included in the development of your procedures. A description similar to that presented in Section 12.1.2 will be acceptable to supply the information called for in Section 12.1.3 of Regulatory Guide 1.70, Revision 2.

331.2 Provide your analysis of the deposition and buildup of activated (12.2.1) corrosion products (crud).

Include estimates of the a.T.ount of deposited crud which may buildup over the plant life. Explain how such crud source term' estimates are factored into the shielding design and expected dose rates. This information is called for in Section 12.2.1 of Regulatory Guide 1.70, Revision 2.

331.3 Provide tabulations by nuclide of the expected airborne concen-(12.2.2) trations of radioactivity in areas normally occupied by operating personnel.

Include tabulations of the expected airborne concentrations of radioactivity which result from these sources:

1) removal of reactor vessel head and internals.

2) relief valve venting.

3) movement of spent fuel.

Describe the models and parameters which are used in calculating

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these concentrations.

This information is called for by Section 12.2.2 of Regulatory Guide 1.70, Revision 2.

331.4 Describe the features and considerations included in your (12.3.1) design to reduce radio-cobalt production and build-up.

Explain what use will be made of the following methods of cobalt reduction:

1) The use of reduced nickel in primary coolant system alloys.
2) Low cobalt impurity specifications in primary coolant system alloys.

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3) Te r.R.Y m i.r o f hipi :oM N, h e facing...-

(;2.3.1) macerials in the primary ;cciant sy; tem.

4) The use of high flow rate /high temperature filtration.

5)

Tha s ? lac nyi of vahas m pf

  • w a. h i s cc. r.m n cr." ou iidJp and ca.n tariance. '

6)

Provisions for decontamination of components and systems containing buildups of cobalt.

7)

Continuous monitoring and adjustment of oxygen con-centration and pH in the coolant.

This information is called for by Section 12.3.1 of Regulat'ory Guide 1.70, Revision 2; this subject is an item of generic concern to the ACRS.

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331.5 Describe the features you have included in the design to ensure (12.3.1) that occupational dose will be ALARA during. decommissioning.

Information submitted in response to requirements of Section 12.3.1 of Regulatory Guide 1.7C Revision 2 can be referenced or used as applicable. This subject is an item of generic concern to the ACRS.

t 331.6 Provide an illustrative example of each of the following com-(12.3.1 )

ponents describing how they are designed to minimize occupational dose:

liquid filters, demineralizers, ventilation filter trains, recombiners, tanks, evaporators, pumps, heat exchangers, recirculation pumps, valve operating stations, sampling station, and valve galleries.

Include layout drawings and diagrams of these examples showing the radiation protection design features.

This information is called for in Section 12.3.1 of Regulatory Guide 1.70, Revision 2.

331.7 Regulatory Guide 8.8, Revision 2, recommends that either 1) there (12.3.1 )

should be no field routing of piping for radioactive materials, or 2) the field routing should be accomplished under the guidance of an engineer familiar with the principles of radiation protec-tion.

Describe how you will implement this recommendation or justify your alternatives.

331.8 Explain what use is made of these ALARA design considerations (12.3.1) which are suggested in Regulatory Guide 8.8, C.2, Revision 2:

1) Sloping of piping runs and tank bottoms.
2) placement of drain tap-offs at low points.

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. 3)

S n.-74n c c f con.uai ;a s uin t...: -;a e line of piping.

4) Avcidance of dead legs and low points in piping.

5) iloia:ce a f I con.ucis.u in j;p mg.

6) Use of large radius bends or elbows in piping.
7) Use of butt welding and consumable inserts.
8) Use of canned pumps and flushable seals.
9) Use of short pipe runs and large diameter piping.
10) Provisions for remote filter changing,
11) Provisions for adequate equipment laydown space inside cubicles.

331.9 You have indicated (FSAR Section 12.1.2.lb) that you place major (12.3.1) sources of radioactivity in individually shielded cubicles as suggested in Regulatory Guide 8.8, Revision 2.

However, numerous major sources on level 437' of the radwaste building are not individually shielded.

(For example, floor drain collector-tank, waste collector tank, chemicul waste tanks, distillate tanks, gas coolers.)

Justify the absence of individual shields for these sources in light of your commitment to keep occupational dose ALARA.

331.10 Describe the functions which your fixed area and airborne radio-(12.3.4) activity monitoring systems are expected to perform in the event of an accident.

This information is called for in Section 12.3.4 of Regulatory Guide 1.70, Revision 2.

331.11 Provide an analysis of the capability of your airborne radioactivity (12.3.4) montioring systems to detect MPCa levels of airborne radiciodine and particulates. An acceptable analysis should explain, for example, how long the systems will take to detect MPCa levels of Iodine-131 I

and Cesium-137 in the rooms of lowest ventilation exhaust. The analysis should encompass areas which have the potential for air-bo,rne contamination and are normally accessed by personnel.

Section 12.3.4 of Regulatory Guide 1.70, Revision 2 calls for information on the sensitivity of monitoring systems.

, 331.12 Provide your estimates of the man-rem doses which workers (12.4) will receive. These estimates should be based on 1) the tasks to be performed during operation and anticipated occurrences,

2) the time and maapower reTJirad to perform those tas4 d'd M the hp*Ctad ac5e M MS In d I +/ e i s 'I f d i. J.o rn d " id iG -

activity to which workers will be exposed in performing those tasks.

Evidence should be provided that your estimates are i

based on these factors. An acceptable method of providing such evidence is:

1) Present selected parts of the detailed analysis as illustrative examples.
2) Summarize the detailed information for all other tasks.
3) Present the total estimated annual occupational dose (man-rems).

This information is called for by Section 12.4 of Regulatory Guide 1.70, Revision 2.

331.13 Describe your equipment decontamination and portable monitoring (12.5.2) instrument calibration facilities. Also, specify the locations of these facilities on Figures 12.3-1 through 12.3-8 as you did.

the other health physics facilities listed in FSAR Section 12.5.2.

This information is called for by Section 12.5.2 of Regulatory Guide 1.70, Revision 2.

331.4 Describe how you will monitor airborne iodine radioactivity (12.5.3) using the portable air monitoring equipment specified in Table 12.5-1.

4 Section 12.5.3 of Regulatory Guide 1.70, Revision 2 calls for information on the methods of evaluating airborne radioactivity.

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