ML20214G925
| ML20214G925 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 04/19/1978 |
| From: | Kreger W Office of Nuclear Reactor Regulation |
| To: | Varga S Office of Nuclear Reactor Regulation |
| References | |
| CON-WNP-0218, CON-WNP-218 NUDOCS 8605230047 | |
| Download: ML20214G925 (5) | |
Text
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APR
- 31373 f!EMOPAND151 FOR:
S. Varga, Chief, Light Water Reactors Branch 4, DP*1 FR0't:
W. Kreger, Chief, Radiological Assessnent Branch, DSE
SUBJECT:
WPPSS-2 ACCEPTANCE REVIEW PLNIT ? TAME: WPPSS fluclear Pro. ject "fo. 2 LICEtiS!!iG STAGE: CL DOCKET ft!!!3ER: 50-397 flILESTONE NtP.9ER/ BRANCH CODE: 01/33 PROJECT !WlAGER:
H. Lynch FISPOMSIBLE BPfliCil: LUR-4 PEflUESTED CO."PLETIO?! PATE: 4/19/78 DESCRIPTIO*l 0F RESP 0ftSE: Reference to original acceptance review REVIEW STATUS: Acceptance review complete The Radiation Prntcction Section of the Radiological Assessment Granch has reviewed Chapter 12 and infomation referenced in Chritor 12 of the WPPSS 2 FSAR tendered on 3/24/73. As ue stated in our 4/14/77 mmo to you, the FSAR provides sufficient inferration for us to begin cur review. 'tcquests for infomation called for by Pcquistory Cuido 1.70, Revision 2, but not included in the FSAR, were sttached to the 4/14/77 meno. We have no additional requests for inforr'ation, and ue have attached a copy of the 4/14/77 requests for your convenienco.
This review was Perfomed by R. Erch, FPS /RAB.
pririnal slene.f by 3Y. E. Kn ger William E. Kroger, Chief Radiologics1 Assestmnt Branch Division of Site Safety and Environmental Analysis
Enclosure:
as stated cc:
R. Hartfield (w/n encl.)
S. Hanauer D. Vassa11n DISTRIBUTION
- 11. Denton J. Collins Docket File D. l4u11er T. !'ur$?
DSE Reading L. Crccker R. Emch RAB Reading P. Vollner W. Kreger D. Crutchfield R. Boyd 0605n30047 7sO43, ft. Lynch PDR ADOCK 05000397 A
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331.0 P.ADIOLGMCAL ASSES 3'OT 331.1 Describe how information from operating CUR experience is (12.1.3) included in the development of the radiation erotectinn n Section 12.1.2 on distgn considerations saecifically dascrloescedures..
your ir.:lusion of CWR operating ex?crience into the plan:
design.
However, Section 12.1.3 does not describe how 3'.d 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 analysic of the deposition and buildup of activated (12.2.1) corrosion products (crud). Ir clude estimates of the amount of deposited crud which may buildup over the plant life. Explain how such crud source torm 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 E.
331.3 Provide tabulations by nuclide of the expected r.irborne concen-(12.2.2) trations of radioactivtty in areas normally occupied by operating personnel.
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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 ol' spent fuel.
Describe the models and parameters which are used in calculating these concentrations.
This information is called for by Section 12.2.2 of Regulatory i
Guide 1.70, Revision 2.
331.L Describe the features and considerations included in your (12.3.1) design to reduce radio-cobalt production and butid-up. Explain what use will be made of the following methods of cobalt raduction:
- 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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The cinimization of hign cobait, hard facing wear
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(12.3.1) materials in the primary coolant system.
- 4) The use of high flow rate /high temperature filtration.
5)
The selection of valves and packing caterials ta minimi:e crud buildup and maintenance.
- 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 Regulatory
- Guide 1.70, Revision 2; this subject is an item of generic concern to the ACRS.
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 1.70 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 opera, ting 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.
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331.7 Regulatory Guide 8.8, Revision 2, recommends that either 1) there (12.3.1) should be no fleid routing of piping for radioactive materials, or 2) the field routing should be accomplished under the guidanco of an engineer familiar with the principles of radiation protec-tion. Describe how you will implement this recorrmendation 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) Placemant of connections above the center 1fne of piping.
4)
Avoidanca of dead legs and low points in piping.
- 5) Avoidance of T connections in piping.
6)
Use of large radius bends or elbows in piping.
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- 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 spece inside cubicles.
331.9 You have indicated (FSAR Section 12.1.2.lb) that you place ma (12.3.1) sources of radioactivity in individually shielded cubicles as suggested in Regulatory Guide 8.8, Revision 2.
However major sources on level 437' of the radwaste building are, numerous individually shielded. -(For example, floor drain collector not tanks, gas coolers.) tank, waste collector tank, chemical was 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.
Guide 1.70, Revision 2.This infomation is called for in Section 331.11 monttoring systems to detect MPCa levels o (12.3.4)
I and particulates.
and Cesium-137 in the rooms of lowest borne contamination and are nomally accesse The Section 12.3.4 of Regulatory Guide 1.70, Revision 2 calls for information on the sensitivity of monitoring systems.
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331.12 Provide your estimates of the man-rem doses which workers (12.4) will receiva.
These estimates should be based on 1) the tasks to be performed during operaticn and anticipated occurrences,
- 2) the tica and mannower required to parform those tasks, ar.d 3) the expe....
ose ra tes and levels of airborna racio-activity ta which workers will ba exposed in perfonaing those tasks.
Evidence should be provided that your estimates are based on these factors.
evidence is:
An acceptable method of providing such 1). Present selected parts of the detailed analysis as illustrative exampics.
- 2) Summar!ze the detailed information for'all other tasks.
3)
Present t dose (manhe total estimated annual occupational rems).
This information is called for by Section 12.4 of Regulator'y Guide 1.70, Revision 2.
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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 v -
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
'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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