ML19257D715
| ML19257D715 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 02/01/1980 |
| From: | Brown S VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | Harold Denton, Parr O Office of Nuclear Reactor Regulation |
| References | |
| RTR-REGGD-01.097, RTR-REGGD-1.097, TASK-OS, TASK-RS-917-4 998-112379, NUDOCS 8002050526 | |
| Download: ML19257D715 (14) | |
Text
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VO7CO VIRGINI A CTRIC AND POWER COMP ANY, RICHMOND, VIRGINI A 23261 February 1, 1980 Mr. Harold R. Denton, Director Serial No. 078 Office of Nuclear Reactor Regulation PSE&C/RCN:mac: wang Attn: Mr. O. D. Parr, Chief Light Water Reactors Branch No. 3 Docket No. 50-339 Division of Project Management U.S. Nuclear Regulatory Commission Washington, DC 20555
Dear Mr. Denton:
Enclosed is a copy of the final draf t of ".e PWR near term OL group's general comments on Revision Two of Regulatory Guide 1.97.
Vepco endorses the comments made by the near term OL working group. We are also including plant specific comments for the measured variables listed in Table Two. These coaments apply to North Anna Unit 2 and indicate the feasibility of applying Regulatory Guide 1.97. Our plant specific comments are based on the revised version of Regulatory Guide 1.97 as presented by the working group.
n '
, ,'trul.yourI, jV/ ,
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Senior Vice President - Power ation Enginee'ing r & Construction #
Enclosure 1876 234 soouosu5 M A
NEAR TERM OL GENERIC COMMENTS Table 1 DESIGN CRITERI
, CRITERIA INSTRUMENTATION TYPES 2 A B C D E
- 1. Seismic qualification yes yes yes no n per .m y. _ . , ._ .....
5 7b I6 76
- 2. Single failure criteria per ". ;_Into c C idc 1.:2 g yes yes yes no no 15 uo noh
- 3. yes yes yes 4 -yee-Environmental qualification} }
per.me mmv , - ..ms
- 4. Power source ./ -C2 7
C0 7
~ ." V
- 5. Out-of-service interval a a 8 -+-10 to before accident
- 6. Portable no no no ll no ll no ll
- 7. Quality assurance level 12 12 12 --to k- AN 0
- 8. Display type l3 Conl4 Con 14 0C; D' d OD15 ODIS
- 9. Display method Recl8 Recl7 Recl7 Ind ia Ind i a,19
- 10. Unique identification yes yes yes no no
- 11. Periodic testing per yes yes yes No
.yee- no
=.:= ,=.-
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- c a '
J m ;u .. suit . , o co m.sevam m . tc m;aitm.s in 2.L. Sm.1 ing , c f f1_at and cn U . . amu-al a.vultu.s, mmm f amalm ins t-~ ;s f; . .x a m. . 3 .mdicti-- -. ..
O a:,,-+;
2jpeATjhoseinstrumentsthatprovideinformationrequiredtotakepreplanned y
manual actions.
Type B - Those instruments that provide information to monitor the process of accomplishing critical safety functions.
Type C - Those instruments that indicate the potential for breaching or the ac-tual breach of the barriers to fission product release.
Type D - Those instruments that indicate the performance of individual safety systems.
Type E - Those instruments that provide information for use in determining the magnitude of the release of radioactive materials and for continuous-ly assessing such releases, for defense in depth, and for diagnosis.
' Eau av.va .u m . m v . :., saum.u ..m.m .:.m .ms u m ..~ u o v .05: N22: 197 2 , Sect +on-h cad /cr Sectier ?' '. '! , 2 : 2pprcpri2t_
1.97-9 (Footnotes continued) 1876 2E
NEAR TERM CL GENERIC COEUS Footnotes continued for Table 1 .
- See paragraph 6.3.6 of Draft Standard ANS-4.5.
5 0.clificd - th; c:ndit.:c; cf .t: :p ::ti r c;J, f:: :licti:^ ~2 nit:rt,
/J::! ' 320 1^ 7; .
%. . w..:: ;a : u:::
74 .. . 4 - __. _ _ _ _ _ e _ c. ._ 3r m ,,,
8 Paragraph 4.11, " Exemption", of IEEE Standard 279-1971.
9 Based on normal Technical Specification requirements on out-of-service for the safety system it serves.
loNot necessary to include in the Technical Specifications unless specified by other requirements.
11 Radiation monitoring outside containment may be portable if so designated in Tables 2 and 3.
12 Level of quality assurance per Appendix B to 10 CFR Part 50.
13 Continuous indication or recording displays a given variable at all times; intermittent indication or recording displays a given variable periodical-ly; on-demand indication or recording displays a given variable only when requested.
14 Continuous display.
15 Indication on demand.
- 18Where trend or transient information is essential to planned operator ac-tions durine and after an accident.
- 17 Recording for those parameters for which trend or historical information is reauired durine and ,f ter an accident.
- 1aDial or digital indication.
19 Effluent release monitors require recording, including effluent radioactivity 2
monitors,environsexposureratemonitors,andmeteorqlogymonitog.
h dia:La mum m.m
^
__m . c.-m.m., ,_ .m m_m% -..m
- q.icc. :au ~ ::::: ?:320-1979.
21 Class "IE" Power.
22High Reliability NON-IE Power Source battery backed when momentary interrup-tion is not tolerable for the connected equipment.
23 Types A, B & C - assume LOCA environment for in-containment instruments.
Types D & r - assume worst case non-accident environment for in-containment instruments.
24 Purchased to " commercial grade" standards with installation and engineering practices consistent with Muclear Power Plant applications.
2sFSAR Licensing Coc:mitmec . . for safety grade equipment.
2sSingle failure criteria can be met by using either redundant inputs from a given parameter or by diversity thr.agh inputs from different Instrumentation Types (A, B or C) for the given parameter or by independent diverse parameters.
- = indicates notes where Near Ters OL Group added underlined portions.
1876 236
Table 2 s
PWR VARIABLES Measured Variable Range Type Purpose Near Term CL Group Ceneric Comments Plant Specific Comunents CCRE lg Q Core East Temperature 150*F to '- s ,
h ANS-4.5, Section 6.2. 3.
To provide ancore temperature Change 50 to 16 as this is a reasonable cross section.
Extend range of 16 of 50 existing 0-700of thermocouples to 1650cF .
measurements to identify localiaed 1650 F is ab<.,ut 2> Critical Temperature will require adJitional switch-hot areas. (Approximately. W and T/C with stainless steel sheath will able display.
measurements) 4/psha* maintain physical capability to 1650 F Control Rod Position Full in or not
{ To provide positive indication that Mechanism power is adequate means to as- No change.
full in the control rods are fully inserted, sure rods are on bottom. Accident plus gggy pogR -( M* : * * *4 st uc k rods shich requi r_es correc tive ac-OR c4lon D Neutron Flux 1 c/ s t o 11 powe r E ANS-4.5, Section 6.2.2. Fission counter would be destroyed in No change.
For indication of appro4ch to normal power oper ation.
) criticality.
RIACTO't COOLA.%7 SYSTEM RCS Hot leg Temper- 150*F to 150*F B ANS-4.5, Section 6.2.3. Change existing 0-7000 F rarge to ature To aid in determining reactor system accomodate 75Lfr max.
subcooling and to provide indication Existing device does not meet of natural circulation. quality assurance.
RCS Cold Leg Temper- 150*F to 750*F B ANS-4.5, Section 6.2.3. Change existing 0-70t1'F range to ature To provide indicattun of natural accomodate 75f F max.
circulation; to provtde input for Existing device does not meet heat balance calculations; to quality assurance.
s provide direct indication of ECCS injection.
RCS Pressure N ..,....m B,C ANS-4.5, Sections 6.2.3 and 6.2.4. The range of this measuresent has been 0-3000 psia range no change.
@ psig For indication of an accident and limited to 3000 psig since this may be Add 0-4000 psia transmitters to indicate that actions must be the current easimum range ava.lable in taken to mitigate an event. a qualified pressure transmitter. It N
should be noted, however, that this y transmitter should be ab?e to withstand pressurization up to 40.0 lbs without damage to the t ransmit ter or a sig-nificant shift in calibration.
EU PRtishlRE 'O fo 4000 eq E a is suggested that . singie type E 4000 psig transmitter be added to assure coverage of the short duration high presuite transient associated with ATVS phm a . ni.
RC 1.9 7-11 i
Table 2 (continued)
PWit VAR! ABU S Neasured Variable Range Type Purpose Near Tere 01 Group Generic Comnents Plant Specific Comments Pressurtzer Level -H+ B,D ANS-4.5, Section 6.2.3.
7 , To assure proper operation of the No change,esisting wide range Pressuriier and to assure safe 9.97 - 399.03 inches.
DE %@c -
operation of heaters. It is also used in conjunction with changes in reactor pressure to determine leak and voto sizes.
Degree of Subcoolin 200*F subcooling to E For indication of margan in core No change.
35'F superheat cooling and the need for emergency coolant additions or reductions as the margin changes and to obviate the necessity to consult stese
,/ tables.
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Iw' VARIAFl.F3 nessured Varsable Range Type P u r po u- Sca r Term OL Group Ceneric Comment s Plant Specific Cecnents CMT Al s'*. INT (Coatinued)
Cont a irusent Isola- Closed-not closed B,D ANS-4.5, Section 6.2.5. I f not subject to single failure, do not Requalify necessary position sen-tson Valve Position To indicate the status of contain- need redundant indication, sors on A0V's, redundant indication ment isolat ion and t o pr ovade is not feasible.
.nformation on the st atus of valves in process lines that could carry radioactive materials oct of containment.
Containment Sump Narrow range (sump). C ANS-4.5, Section 6.3.3. Plant specific - NSSS vendor should con- No change.
Water Level Wade range (bottom f or indication of leakage within firm needed inventory.
of containment to the containment and to ensure Type B requirements have been eliminated J.*( 83M1. t a l_D adequate inventory for performance consistent with appropriate use of the
$9 P ' l I g (, )
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Hagh-Range Cc.atain- I to 107 R/hr ment Area Kadiation C
E to seir identiev if an accident riant srecific. see ac i ioi- "'" '" ""' " '-
(60 kev to 3 *!cV has degraded beyond calculated Type B requirements have been clininated photons with 120% values and to indicate ats magni- consistent with appropriate use of the accuracy for tude to determine action to variable.
photons of 0.1 to protect the public.
3 Mev)[107 R/hr for photons is approximately equivalent to 10s rads per hour for betas and photons]
SECONDARY SYSTEMS Steam Generator From atmospheric D For indication of integrity of the No change.
Pressure pressure to 20% secon Sry system and an anJication above safety value of capability for decay heat setting removal.
Steam Gener3 tor Level From tube sheet to D For indication of intega '* M ".ne Steam generator wide range level. Existing wide range 7 to 41 feet.
separators secondary system and an indication of capability f or decay heat OR 54Wloca4E Lc v'e L removat.
Auxilaary Fredwater 0 to 110% design D To indicate an adequate source of No change.
Flow flowl water to each steam generator upon loss of main feedwater.
" C' O to 110% design E To indicate an adequate source of Main fccJwater flow is not required as a p"g; / flowl water to cach stcJee "fnerator. type E variable.
O feed flow only indicates water into each SG; it does not indicate an ade nuate source of water to each steam generator.
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Table 2 (Continued) PW VARIABLES Range Type Purpose Near Ters OL Group Generic Comments __ "ra wre i Va r i ab l e lhnfiMER.C10 "MERI AI.S FEIF ASED ACTIVE IK1 TE FIANT See Reg. Guide 1.101 for radiation (Cettinued) monitoring. Auxilia ry Building 10 to 103 p-i/cc i nc l ud in it t>u a l d i n g s Xe-133 calibration centatr.ing primary systein giscs, e.g., waste ges deray tana - Other Relene 10 ~7 to 102 pCi/cc Paints (including XE-131 calibration fuel handling area af separate trom (permanently Aut t ita ry building) installed monitors) Ef fluent Radioactiv- 10'3 to 102 pCi/cc E To prsvide the operator with Lty - liigh-Range intornation regarding release of j1I (permanently Radiohalodens and radioactive halogens and particu-Particulates installed lates. Continuous collection h monitors) of representative samples followed by monitoring (measurements) of j samples for radionalogens and for particulates. J Environs Radioactiv- 10_s to 102 R, h r E ANS-4.5, Section 6.3.4. d ity - Exposure Rate (60 Fev to 3 PcV) For estimating release rates of g (permanently radioactive materials released during an accident from unidenti-installed fied release paths (not coverco moottors) by effluent monitors) - contanuous readout capability. (Approxamately 16 to 20 locations - site depen-dent.)
~
Environs Radioactiv- 10'S to 10 3 mci /cc E For estimating release rates of sty - Radiohalogeris for both radio- radioactive siterials released and Partstulates halerens and during an acca. lent from untdenti-parttrulates fico release patha (not covered by effluent monitors). Continuous (p. c.nanently collection of representative installed s.iniples followet by monatoring i gr plers) (acasun ment:.) of the samples. ( App ro x i mi t.- ly 14 to 20 locations - site lep'rlaut. s Q RG l.97-17 -' N b ( J1
Table 2 (Continued)
- PWR VAR _I A_ S__T.E__S
% sured Vartable Range Type Purpose Near Tern OL Group Ceneric Comments thrnE PADIOLCTIVE
" M Wit!S D 11ASFD H.0M THE PIANT (Contanued) See Reg. Guide 1.101 for radiation sonitoring.
Plant and Environs High R_anee E During and following an accident, Redtoactivity 0.1 to 104 R/ar (portable anstruments) to monitor radiataoa and airborne photons radioactivity concentrataons in g 0.1 to 104 rads /br saany areas throughout the facility betas and low- and the site environs shcre it is j - energy photons impractical to install stationary U.) monitors capable of covering both normal and accident levels. 100-channel E Duririg and following an accident, gaana-r a y to rapidly scope and composation spectrometer of gamma-emitting sources. POST;CClrENT SAtiPLING CAPALILITY Pramary Coolant As requirci based E ANS-4.5, Section 6.3.2. Sum; s We agree that these capabilities are on Regulatory To provide means for sa fe and a licensee function, however, they do Containment Air Cuade 1.4 guide- convenient sampling. These not lines provisions should include: fit the '* type" definitions- A through E as stated in this guide. It5TACCIDf5f ANALYSIS 1. gamma-ray E 1. Shielding to maintain radiation CAPABILITY (ON-SITE) spectrum We agree that these capabilities are doses ALARA, a licensee function, however, they do
- 2. pn 2. Sample containers with container-
- 3. hydrogen sampling port connector compati-not fit the " type" definitions A through
- 4. oxygen E as stated in this guide.
bility,
- 5. boron 3. Capability of sampling under pr imary system pressure and negative pressure,
- 4. Handling and transport capabi-lity, and
- 5. Pre-arrangement for analysis and interpretation,
- i. I. ' ".O! OGY
' in1 Direction 0 to %0* (!5' E For determining ef fluent transport See Reg. Guide 1.23 , acceir et y wi t h a direction for emergency planning,
[ .tefterti m of li* dase as cssment, and tourre esti-n 2...., d.. , a .. o. r. 4.'.. , iI , ;,n p ) s J CD N .N uc .u-ia d & V N . . ON
Table 2 (Continued) PkR VARIABLES Ne a sure i Variable Raage Type Purpose Near Tern OL Group Generic Comments A~
,rricxpIOGY See Reg. Guide 1.23 (Continued)
Vind Speed a to 30 mps (67 E For determining effluent travel sph) (10.22 mps speed and dilution for emergency (0.5 mph) accuracy planning, doses assessments, and for wind speeds source estimates. less than 11 ops (25 mph), with a starting thres-
. hold of less than u.45 mps (1 m;b))
Ter; e ra t u re -50*F to 120'F E For determining nature of precipitation kl} (t0.9'F accuracy) and ground deposition for emergency y, planning. (d Vertical Temperature -9'F to +9*F E For determining ef fluent dif fusion Height requirements appear unreasonable. _J Difference (10.3*F accuracy rates for emergency planning, dose gj per 164-foot assessments, and source estimates. () antervals) Precipitation Recording rain E For determining ef fluent transport gage with range and ground deposition for emergency sufficient to planning. ensure accuracy of total accumu-lation within 10%
- of recorded value
- 0.01" resolution
' -J C]hN ii 1.97-i9 N'
aps. - N}}