ML18019A286

Forwards Addl Info Re Reactor Vessel Level Indicating Sys (Rvlis),Per Sser License Condition.Info Documents Comparison of Emergency Operating Procedures (EOP) That Incorporate Westinghouse RVLIS Sys W/Generic EOP Guidelines

ML18019A286
Person / Time
Site:	Harris
Issue date:	07/16/1985
From:	Zimmerman S CAROLINA POWER & LIGHT CO.
To:	Harold Denton Office of Nuclear Reactor Regulation
References
NLS-85-240, NUDOCS 8507260041
Download: ML18019A286 (10)

Text

REGUL ATO~INFORMA T ION DISTRIBUTION TEH (R IDS)>~.AC~ESSION NBR: 8507260041 DOC~DATE: 85/07/16 NOTARIZED:

NO FACIL:50-400 Shearon Har r is Nuclear Power Plantg Unit 1~Carolina AUTH BYNAME AUTHOR AFFILIATION ZIMMERMANrS.R, Car ol ina Power L Light Co~RECIP~NAME.RECIPIENT AFFILIATION DENTON~H.RE Office of Nuclear Reactor Regulationg Director DOCKET-'05000000

SUBJECT:

Forwards addi info re reactor vessel level indicating.

sys'RVLIS)<per SSER license condition+Info documents-comparison of emergency operating procedures (EOP)that incorporate>>

Westinghouse RVLIS sys w/generic EOP guidelines.,Lt DISTRIBUTION CODE: B001D COPIES RECEIVED:LTR gENCL L SIZE:='ITLE: Licensing Submittal:

PSAR/FSAR Amdts 8, Related Correspondence'OTES:

RECIPIENT ID CODE/NAME, NRR/OL/AOL NRR LB3.LA INTERNAL: ACRS 41 ELD/HDS1 IE/DEPER/EPB 36 NRR ROErM~L NRR/DE/CEB 11 NRR/DE/EQB 13 NRR/DE/HEB 18 NRR/OE/SAB 24 NRR/DHFS/HFEBPO NR R/OHF S/P SR B NRR/OS I/AEB 26 NRR/DSI/CPB 10 NRR/OS I/ICS8 16 NRR/OS I/PSB 19 NRRIOS I/RSB 23 RGiV2 EXTERNAL: 24X DMB/DSS (AMDTS)NRC PDR 02 PNL GRUELgR COPIES LTTR ENCL 1 0 1 0, 6 1 0 1 1 1 1 1 2 2 1 1 1 1 1 1 1 ,1 1 1 1 1 f 1 1 1 1 3 3 1 1 1 1 1 1 1 RECIPIENT ID CODE/NAME NRR LB3 BC BUCKLEY'S 01 ADM/LFHB IE;, FILE IE/DQA VT/QAB21 NRR/DE/AEAB NRR/DE/EHEB NRR/DE/GB 28 NRR/DE/HTEB 17 NRR/DE/SGEB 25 NRR/DHFS/LQB 32 NR R I D L'/S 8 P 8 NRR/DS I/ASB NRR/DS I'/CSB 09 iVRR/DS I/HETB 12 RAB 22 REG FILE 04 RIB BNL(AMDTS ONLY)LPDR.03-NSIC'5 COPIES LTTR ENCL 1 0 1 1 1 0 1 1=1 1 1 0.1 1 2 2 1 1 1 1 1 1 1 0 1 1 1 1 1 1 1 1 1 0.1 1 1 1 1 1 TOTAL NU>>>>lBER OF COPIES REQUIRED LTTR 52 ENCL f I

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~0 Carolina Power 8 Light Company JUL 1 6 1985 SERIAL: NLS-85-200 Mr.Harold R.Denton, Director Office of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT UNIT NO.I-DOCKET NO.50-000 REACTOR VESSEL LEVEL INDICATING SYSTEM

Dear Mr.Denton:

Carolina Power R Light Company (CPRL)hereby submits additional information concerning the Shearon Harris Nuclear Power Plant (SHNPP)Reactor Vessel Level Indicating System (RVLIS).This information is submitted in response to the Safety Evaluation Report (SER)license condition concerning Inadequate Core Cooling Instrumentation.

As discussed on page 0-0 of SER Supplement l, the NRC requires that prior to criticality CPRL demonstrate that the SHNPP Emergency Operating Procedures (EOP)that incorporate the generic Westinghouse RVLIS system conform to generic EOP guidelines relating to the use of the RVLIS, or that deviations be identified and explained.

The attached information documents CPRL's completion of this evaluation.

If you have any questions concerning this subject or require additional information, please contact me.Yours very truly, 3HE/ccc (1670GAS)Attachment S.Zi merman nager Nuclear Licensing Section Cct Mr.B.C.Buckley (NRC)Mr.G.F.Maxwell (NRC-SHNPP)

Dr.3.Nelson Grace (NRC-RII)Mr.Travis Payne (KUDZU)Mr.Daniel F.Read (CHANGE/ELP)

Wake County Public Library Mr.Wells Eddleman Mr.3ohn D.Runkle Mr.G.A.Schwenk Dr.Richard D.Wilson Mr.G.O.Bright (ASLB)Dr.3.H.Carpenter (ASLB)Mr.3.L.Kelley (ASLB).85072b004i 85071 b.PDR'ADOCN 05000 E'11 Fayettevilte Street~P.O.Box 1551 o Raleigh, N.C.27602 V I' ATTACHMENT The Westinghouse Owners'roup Emergency Response Guidelines (ERG)Revision I, high pressure version incorporates a generic Reactor Vessel Level Indicating System (RVLIS)which is described in the executive volume of the ERGs under the generic issues section entitled,"Reactor Vessel Liquid Inventory System." A comparison of the generic RVLIS against the Reactor Vessel Level Instrument System Manual that describes the SHNPP RVLIS system shows that the SHNPP RVLIS is consistent with the generic RVLIS in terms of instrument readout capabilities (i.e., upper range/full range/dynamic head range)and application of RVLIS reading to different plant situations.

Enclosures l and 2 contain the necessary cross-reference information to show that the plant specific use of RVLIS in SHNPP EOPs conform to the generic ERGs relating to the use of RVLIS.Enclosure 2 lists the comparison between generic and plant specific usage of RVLIS and any deviations are identified and explained.

(1674GAS/ccc

)

Q.

ENCLOSURE I: EOP TITLE CROSS REFERENCE CPRL WOG Guidelines Title EPP-I EPP-2 EPP-3 EPP-0 EPP-5 EPP-6 EPP-7 EPP-3 EPP-9 EPP-10 EPP-I I EPP-12 EPP-13 EPP-IO EPP-15 EPP-16 EPP-17 EPP-13 EPP-19 EPP-20 EPP-21 EPP-22 ECA-O.I ECA-O.I ECA-0.2 ES-O.I ES-0.2 ES-0.3 ES-0.0 ES-I.I ES-1.2 ES-1.3 ES-1.0 ECA-I.I ECA-1.2 E-2 ECA-2.1 N/A ES-3.1 ES-3.2 ES-3.3 ECA-3.1 ECA-3.2 ECA-3.3 Loss of AC Power to IA-SA and IB-SB Busses Loss of All AC Power Recovery Without SI Required Loss of All AC Power Recovery With SI Required Reactor Trip Response Natural Circulation Cooldown Natural Circulation Cooldown With Steam Void in Vessel (with RVLIS)Natural Circulation Cooldown With Steam Void in Vessel (Without RVLIS)SI Termination Post-LOCA Cooldown and Depressurization Transfer to Cold Leg Recirculation Transfer to Hot Leg Recirculation Loss of Emergency Coolant Recirculation LOCA Outside Containment Faulted Stea'm Generator Isolation Uncontrolled Depressurization of All Steam Generators SGTR Isolation Post-SGTR Cooldown Using Backfill Post-SGTR Cooldown Using Blowdown Post-SGTR Cooldown Using Steam Dump SGTR With Loss of Reactor Coolant: Subcooled Recovery SGTR With Loss of Reactor Coolant: Saturated Recovery SGTR Without Pressurizer Pressure Control FRP-S.I FRP-S.2 FRP-C.I FRP-C.2 FRP-C.3 FRP-H.I FRP-H.2 FRP-H.3 FRP-H.O FRP-H.5 FRP-P.I FRP-P.2 FRP-3.1 FRP-J.2 FRP-3.3 FRP-I.I FRP-I.2 FRP-I.3 FR-S.I FR-S.2 FR-C.I FR-C.2 FR-C.3 FR-H.I FR-H.2 FR-H.3 FR-H.O FR-H.5 FR-P.I FR-P.2 FR-Z.I FR-Z.2 FR-Z.3 FR-I.I FR-I.2 FR-I.3 PATH-1 E-0 2 E-I PATH-2 E-3 Response to Nuclear Power Generation/ATWS Response to Loss of Core Shutdown Response to Inadequate Core Cooling Response to Degraded Core Cooling Response to Saturated Core Cooling Response to Loss of Secondary Heat Sink Response to Steam Generator Overpressure-Response to Steam Generator High Level Response to Loss of Normal Steam Release Capability Response to Steam Generator Low Level Response to Imminent Pressurized Thermal Shock Conditions Response to Anticipated Pressurized Thermal Shock Conditions Response to High Containment Pressure Response to Containment Flooding Response to High Containment Radiation Level Response to High Pressurizer Level Response to Low Pressurizer Level Response to Voids in Reactor Vessel Reactor Trip or Safety Injection/Loss of Reactor Secondary Coolant Steam Generator Tube Rupture NOTE: This cross-reference list may change depending on future WOG ERG revision and plant specific needs.(1674GAS/ccc

)

ENCLOSURE 2: RVLIS CROSS-REFERENCE l.2.3.5.6.7.8.9.10.11.12.13.10.15.16.17.18.19.20.21.22.23.20.25.26.SHNPP EOPs EPP-6/la EPP-6/15 EPP-6/2 1c EPP-12/13a EPP-12/18a EPP-21/15 EPP-21/19b EPP-22/8c EPP-22/12 Foldout I/a 2)Foldout 3/a 2)FRP-C.1/6a FRP-C.1/16c FRP-C.1/23 FR P-C.2/5a FRP-C.2/7a FRP-C.2/18 FR P-P.I/5 FRP-P.1/12 FRP-I.3/8b FRP-I.3/10 FRP-I.3/18 FRP-I.3/20 PATH-2/J-9 CSF-2 CSF-6 WOG ERGs ES-0.3/la ES-0.3/5 ES-0.3/11c ECA-l.1/13a E CA-l.1/18a ECA-3.2/16 ECA-3.2/20a ECA-3.3/7c ECA-3.3/11 ECA-3.2 Foldout/1 ECA-3.3 Foldout/1 FR-C.I/6a FR-C.1/16c FR-C.1/23 FR-C.2/5a FR-C.2-7a FR-C.2/18 FR-P.1/5 FR-P.1/12 FR-I.3/8b FR-I.3/10 FR-I.3/18 FR-I.3/20 E-313S F-0.2 F-0.6 Differences None None None None None See Note 1 See Note 1 None None See Note 1 See Note 2 None None None None None None None None None None None None None None None NOTE 1: NOTE 2: The generic guidelines only allow the operator to run one RCP as part of ERG recovery actions.The plant specific EOPs allow the operator to run more than one RCP and therefore the plant specific steps account for more than one RCP running.The ERG step only gives guidance for no RCPs running.The SHNPP EOP step contains additional guidance to account for possibility that RCPs are running.(1674GAS/ccc)

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