ML19221B065
| ML19221B065 | |
| Person / Time | |
|---|---|
| Issue date: | 03/31/1979 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| References | |
| NUREG-75-087, NUREG-75-087-09.5.2, NUREG-75-87, NUREG-75-87-9.5.2, SRP-09.05.02, SRP-9.05.02, NUDOCS 7907120342 | |
| Download: ML19221B065 (2) | |
Text
NU R EG-75/087 p Arco cf Q
f U.S. NUCLEAR REGULATORY COMMISSION
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.c h4 STANDARD REVIEW PLAN
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OFFICE OF NUCLEAR REACTOR REGULATION SECTION 9.5.2 C0f1MUNICATIONS SYSTEMS REVIEW PESPONSIBILITIES Primary - Power Systers Eranch (PSB)
Secondary - None AREAS OF REVIEW The PSB review of the corrunication sy stem is limited to that portic of the system used in intra-plant and plant-to-of fsite corrunications during transien.
ire and accident cceditions. Tne system is reviewd with respect to the follcwing cansiderations: capa-bility of the system to provide ef fective intra-plant corrunications and effective plant-to-offsite corrunicaticns during transient, fire ard accident conditions, including loss of offsite pcwer.
The Energency Planning Branch (EPB) verifies that the offsite corrunication syster provided will satisfy e ergency plar, reuuirerents, including notification of perscnnel and irplecen-tation at evacuatien peccedures (SRP Section 13.3).
II.
ACCEPTANCE CRITERIA Acceptability of the design of the corranication systen, as described in the applicart's safety analysis report (SAR), is based in part on the degree of similarity of the design witn that for previcJsly reviewed plants with satisfactory operLting egerience. There are no general design criteria or regulatory cuides that directly apply to the safety-related perfornance requirerents for the corrunication system. The PSB will use the following critericn to assess tFe system design c3pability: the connunica+'on s; sten is acceptable if the integrated design of the systen will provide effective cora mication tetween plant personnel in all vital areas during the full spectrum of accident or incident conditions (including fire) under "axirur potential noise levels. Corrunications systems for fire fighting are acceptable if they reet the requirerents of Branch Technical Position ASB 9.5-1.
III. PEVIEW PROCEDURES The inforration provided in the SAR pertaining to the design of the corrunicaticn system will be w aluated to cetermine that intra-plant corrunication equipment reeded in vital areas during recovery actions from transient, fire or accident cceditions is provided.
l The reviewer will se'ect and emphasize raterial fron this SRP section, as may be appro-priate for a particular case.
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- ),I c USNRC STAND ARD REVIEW PLAN 9 '/
OLJ Standard cow ew p6ene ere propered for the guedence of the Ofnce of Nuclear Re.etor Reguietion staff respone.ble for the recew of apphcations to construct end e
operste nucteer power paents These documente are made ovestatse to the public es part of the Commiseson e pokey to 6nform the nucteer industry and the general pwuc of regulatory procedu es end pobcsee Standard re.new plane see not subetstutee f or reguletory guedes of the Comm.se.on e regu6stinne end r
comp 4sence.arvth th.em se not rege e ed The stand.ard re. sew plan secteene are keyed to Rowsion 2..of the Stenderd Format and Coatent of Safety Anotys o Reporte f.r.e
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The design basis, design criteria, system description sections, and the analyses t.at demonstrate the eff_ctiveness of the systen when maxinum plant noise levels are being generated during incident and accident conditions are reviewed t.
verify that the corruni-
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cation systen will function effectively. The reviewer uses engineering judgr ent and compares the systen capabilities with equipment prvided for previously approved plants.
The PSB will accept the conrunication system if a staterent ir the SAR commits the appli-cant to perforn a functional test under conditions that simulate the maximum plant noise levels being generated daring the various operating conditions, including fire and acci-l dent condition, to demonstrate system capabilities.
IV. EVALUATION FINDINGS The reviewer verifies that suf ficient infor ation has been providea and that his review supports conclusions of the following type, to be included in the staff's safety evaluation report "The corrunication system includes all corponents for intra-plant anJ plant-to-affsite connunications. The scope d review of the corr'unications systam for the plant included verification that orfsite equipnent is capable of pro-v~*ing for notification cf personrel and inplenentation of evccuation procedJres, and verification that onsite corrunicattom are adequate in the event of an emergcncy.
[The review has determined the adequacy of tne applicant's prcposed design criteria and bases for the conrunication system and the requirements for all plant operation, fire and accident conditicns. (CP)] [The review has deternirej th3t the design of the conmunicatior.s systen and auxiliary supporting systers is in confarrance "ith the design criteria and b3ses (OL)]
"The N sis for acceptancc in the staff reviow has teen conformance of thc acplicant's designs, desigh criteria ada design bases for the cormulications syster and necessary auxiliary supportir q systen: to staf f positions and industry standards, and tb ability of the systems to provide effective cor.runications Letween plant personnel in all
. ital areas durino the full spcctrum of accident or incident conditions under "ax imu"1 potential noise levels.
"The staf f concludes that the design of the convications syster conforms to all applicable guides, staf f positions and industry standards and is acceptable.'
l V.
REFERE'.CES l.
Cranch Technical Pcsition ASB 9.5-1, "Guidelires for Fire Protection for Nuclem Poner Plants" (attached to SPP 9.5-1).
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UCb Rev. I 9,5,2_p