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~INFORMAT ION DISTRIBUTION TEH (R IDS)

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.AC~ESSION NBR: 8507260041 DOC ~ DATE: 85/07/16 NOTARIZED: NO DOCKET-'

FACIL:50-400 BYNAME Shearon Har r is Nuclear Power Plantg Unit 1~ Carolina 05000000 AUTH AUTHOR AFFILIATION ZIMMERMANrS.R, Car ol ina Power L Light Co ~

RECIP ~ NAME. RECIPIENT AFFILIATION DENTON~H.RE Office of Nuclear Reactor Regulationg Director

SUBJECT:

Forwards addi info re reactor vessel level indicating.

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

Westinghouse RVLIS sys w/generic EOP guidelines.

DISTRIBUTION CODE: B001D COPIES RECEIVED:LTR gENCL L SIZE:=

,Lt Licensing Submittal: PSAR/FSAR Amdts 8, Related Correspondence'OTES:

'ITLE:

RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME, LTTR ENCL ID CODE/NAME LTTR ENCL NRR/OL/AOL 1 0 NRR LB3 BC 1 0 NRR LB3. LA 1 0, BUCKLEY'S 01 1 1 INTERNAL: ACRS 41 6 ADM/LFHB 1 0 ELD/HDS1 1 0 IE;, FILE 1 1=

IE/DEPER/EPB 36 1 IE/DQAVT/QAB21 1 1 NRR ROErM ~ L 1 1 NRR/DE/AEAB 1 0.

NRR/DE/CEB 11 1 1 NRR/DE/EHEB 1 1 NRR/DE/EQB 13 2 2 NRR/DE/GB 28 2 2 NRR/DE/HEB 18 1 1 NRR/DE/HTEB 17 1 1 NRR/OE/SAB 24 1 NRR/DE/SGEB 25 1 1 NRR/DHFS/HFEBPO 1 1 NRR/DHFS/LQB 32 1 1 NR R/OHF S/P SR B 1 1 I NR R D L'/S 8 P 8 1 0 NRR/OS I/AEB 26 ,1 1 NRR/DS I/ASB 1 1 NRR/DSI/CPB 10 1 1 NRR/DS I'/CSB 09 NRR/OS I/ICS8 16 1 f iVRR/DS I /HETB 12 1 1 NRR/OS I/PSB 19 1 1 RAB 22 1 1 NRRIOS I/RSB 23 1 1 REG FILE 04 1 1 RGiV2 3 3 RIB 1 0.

EXTERNAL: 24X 1 1 BNL(AMDTS ONLY) 1 1 DMB/DSS (AMDTS)

NRC PDR PNL GRUELgR 02 1

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~ 0 Carolina Power 8 Light Company SERIAL: NLS-85-200 JUL 1 6 1985 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 INDICATINGSYSTEM

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, S . Zi merman nager Nuclear Licensing Section 3HE/ccc (1670GAS)

Attachment Cct Mr. B. C. Buckley (NRC) Mr. Wells Eddleman Mr. G. F. Maxwell (NRC-SHNPP) Mr. 3ohn D. Runkle Dr. 3. Nelson Grace (NRC-RII) Mr. G. A. Schwenk Mr. Travis Payne (KUDZU) Dr. Richard D. Wilson Mr. Daniel F. Read (CHANGE/ELP) Mr. G. O. Bright (ASLB)

Wake County Public Library Dr. 3. H. Carpenter (ASLB)

Mr. 3. L. Kelley (ASLB)

'11 b.

. 85072b004i 8507105000 PDR 'ADOCN E

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 WOG CPRL Guidelines Title EPP-I ECA-O. I Loss of AC Power to IA-SA and IB-SB Busses EPP-2 ECA-O. I Loss of All AC Power Recovery Without SI Required EPP-3 ECA-0.2 Loss of All AC Power Recovery With SI Required EPP-0 ES-O. I Reactor Trip Response EPP-5 ES-0.2 Natural Circulation Cooldown EPP-6 ES-0.3 Natural Circulation Cooldown With Steam Void in Vessel (with RVLIS)

EPP-7 ES-0.0 Natural Circulation Cooldown With Steam Void in Vessel (Without RVLIS)

EPP-3 ES-I. I SI Termination EPP-9 ES-1.2 Post-LOCA Cooldown and Depressurization EPP-10 ES-1.3 Transfer to Cold Leg Recirculation EPP-I I ES-1.0 Transfer to Hot Leg Recirculation EPP-12 ECA-I. I Loss of Emergency Coolant Recirculation EPP-13 ECA-1.2 LOCA Outside Containment EPP-IO E-2 Faulted Stea'm Generator Isolation EPP-15 ECA-2.1 Uncontrolled Depressurization of All Steam Generators EPP-16 N/A SGTR Isolation EPP-17 ES-3.1 Post-SGTR Cooldown Using Backfill EPP-13 ES-3.2 Post-SGTR Cooldown Using Blowdown EPP-19 ES-3.3 Post-SGTR Cooldown Using Steam Dump EPP-20 ECA-3.1 SGTR With Loss of Reactor Coolant: Subcooled Recovery EPP-21 ECA-3.2 SGTR With Loss of Reactor Coolant: Saturated Recovery EPP-22 ECA-3.3 SGTR Without Pressurizer Pressure Control FRP-S. I FR-S. I Response to Nuclear Power Generation/ATWS FRP-S.2 FR-S.2 Response to Loss of Core Shutdown FRP-C. I FR-C. I Response to Inadequate Core Cooling FRP-C.2 FR-C.2 Response to Degraded Core Cooling FRP-C.3 FR-C.3 Response to Saturated Core Cooling FRP-H. I FR-H. I Response to Loss of Secondary Heat Sink FRP-H.2 FR-H.2 Response to Steam Generator Overpressure FRP-H.3 FR-H.3 -Response to Steam Generator High Level FRP-H.O FR-H.O Response to Loss of Normal Steam Release Capability FRP-H.5 FR-H.5 Response to Steam Generator Low Level FRP-P.I FR-P. I Response to Imminent Pressurized Thermal Shock Conditions FRP-P.2 FR-P.2 Response to Anticipated Pressurized Thermal Shock Conditions FRP-3.1 FR-Z. I Response to High Containment Pressure FRP-J.2 FR-Z.2 Response to Containment Flooding FRP-3.3 FR-Z.3 Response to High Containment Radiation Level FRP-I. I FR-I. I Response to High Pressurizer Level FRP-I.2 FR-I.2 Response to Low Pressurizer Level FRP-I.3 FR-I.3 Response to Voids in Reactor Vessel PATH-1 E-0 2 E-I Reactor Trip or Safety Injection/Loss of Reactor Secondary Coolant PATH-2 E-3 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 SHNPP WOG EOPs ERGs Differences

l. EPP-6/la ES-0.3/la None

2. EPP-6/15 ES-0.3/5 None

3. EPP-6/2 1c ES-0.3/11c None EPP-12/13a ECA-l. 1/13a None

5. EPP-12/18a E CA-l. 1/18a None

6. EPP-21/15 ECA-3.2/16 See Note 1

7. EPP-21/19b ECA-3.2/20a See Note 1

8. EPP-22/8c ECA-3.3/7c None

9. EPP-22/12 ECA-3.3/11 None

10. Foldout I/a 2) ECA-3.2 Foldout/1 See Note 1

11. Foldout 3/a 2) ECA-3.3 Foldout/1 See Note 2

12. FRP-C. 1/6a FR-C. I/6a None

13. FRP-C.1/16c FR-C. 1/16c None

10. FRP-C.1/23 FR-C.1/23 None

15. FR P-C.2/5a FR-C.2/5a None

16. FRP-C.2/7a FR-C.2-7a None

17. FRP-C.2/18 FR-C.2/18 None

18. FR P-P. I/5 FR-P.1/5 None

19. FRP-P. 1/12 FR-P.1/12 None

20. FRP-I.3/8b FR-I.3/8b None

21. FRP-I.3/10 FR-I.3/10 None

22. FRP-I.3/18 FR-I.3/18 None

23. FRP-I.3/20 FR-I.3/20 None

20. PATH-2/J-9 E-313S None

25. CSF-2 F-0.2 None

26. CSF-6 F-0.6 None NOTE 1: 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.

NOTE 2: 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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