ML18018B878

Forwards Amend 19 to Fsar,For Shearon Harris Unit 1, Consisting of Miscellaneous Technical & Editorial Changes, Changes to Draft SER Open Items & Revised Positions on Reg Guides in Section 1.8

ML18018B878
Person / Time
Site:	Harris
Issue date:	01/31/1985
From:	Cutter A CAROLINA POWER & LIGHT CO.
To:	Harold Denton Office of Nuclear Reactor Regulation
Shared Package
ML18018B879	List: ML18018B878
References
NLS-84-493, NUDOCS 8502070219
Download: ML18018B878 (11)

Text

REGULATD INFORMA'TION DISTRIBUTION STEM (RIDS)

ACCESSION NBR;6502070219 DOC,DATE: 85/01/31 NOTARIZED; YES DOCKET FACIL:50-000 Shearon Harris Nuclear Power Plantp Unit 1~ Carolina BYNAME 05000400 AUTH AUTHOR .AFFILIATION CUTTERgA,Bg Carolina Power 8, Light Co.

RECIP ~ NAME RECIPIENT AFFILIATION DENTONgH ~ R, Office of Nuclear Reactor Regulationr Director Q ~-~~Qx +MS/gS

SUBJECT:

Forwar ds Amend. 19 to FSAR~consisting of miscel l aneous technical 8 editorial changes<changes to draft SER open items 8 revised positions on reg guides in Section~1.

DISTRIBUTION CODE: B001D COPIES RECE'I VED: LTR <<305 TITLE: Licensing Submittal: PSAR/FSAR Amdts 8, elated Correspondence NOTES:

RECIPIENT COPIES REC IP IENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL' NRR/DI /ADL 1 0 NRR LB3 BC 0 NRR LB3 LA 1 0 BUCKLEYgB 01 1 INTERNAL: ACRS 41 e 6 ADM/LFMB ,1 0 ELD/HDS1 1 0 IE FILE 1 IE/DEPER/EPB 36 1 1 IE/DQA SIP/QAB21 1 1=

NRR ROEgM ~ 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 2B 2 -2 NRR/DE/MEB 1S 1 1 NRR/DE/MTEB 17 1 1 NRR/DE/SAB 29 1 1 NRR/DE/SGEB 25 1 1 NRR/DHFS/HFEBQO 1 1 NRR/DHFS/LQB 32 1 1 NRR/DHFS/PSRB 1 1 NRR/DL/SSPB 1 0 NRR/DSI/AEB '26 1 1 'RR/DSI/ASB 1 1 NRR/DS I/CPB 10 1 1 NRR/DSI/CSB - 09 1 1 NRR/DS I/ICSB 16 1 .1 NRR/DSI/METB 12 1 1 NRR/DS I/PSB 19 1 1 NRR RAB 22 1 1 NRR/DSI/RSB 23 1 1 IL 00 1 1 RGN2 IB 1 0 EXTERNAL: BNL(AMDTS ONLY) 1 1 DM18/DSS (AMDTS) 1 1 LPDR 03 1 NRC PDR 02 1 NSIC 05 1 PNL GRUELgR 1 TOTAL NUMBER OF COPIES REQUIRED; LTTR 51 ENCL 03

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CKQE, Carolina Power & Light Company SERIAL: NLS-84-493 l.8 1 $ 98$

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. 1 DOCKET NO. 50-400 FSAR AMENDMENT NO. 19

Dear Mr. Denton:

Carolina Power & Light Company hereby transmits Amendment No. 19 to the Shearon Harris Nuclear Power Plant Final Safety Analysis Report.

This amendment consists of miscellaneous technical changes, revised positions on Regulatory Guides in Section 1.8, and editorial changes. Additional changes related to Draft Safety Evaluation Report open items are also included. A brief summary and explanation for each change is provided in the attachment to this letter.

Each revised page bears the amendment number. Only those changes that are technical in nature are indicated by vertical bars. Instructions for entering the revised pages are included.

Should you have any questions with regard to this amendment, please contact Ms. Carol Love of our Nuclear Licensing Section staff at (919) 836-81 66.

Yours ery tr A. B. Cut er Vice Pr ident Nuclear Engineering 6 Licensing CGL/ccc (896CGL)

Attachments CC: Mr. B. C. Buckley (NRC) Mr. Wells Eddleman Mr. G. F. Maxwell (NRC-SHNPP) Mr. John D. Runkle Mr. J. P. O'Reilly (NRC-RII) Dr. Richard D. Wilson Mr. Travis Payne (KUDZU) Mr. G. 0. Bright (ASLB)

Mr. Daniel F. Read (CHANGE/ELP) Dr. J. H. Carpenter (ASLB)

Chapel Hill Public Library Mr. J. L. Kelley (ASLB)

Wake County Public Library (

goo A. B. Cutter, having been first duly sworn, did depose and say that the ~(6 information contained herein is true and correct to the best of his information, knowledge and belief; and the sources of his information are officers, employees, contractors, and agents of Carolina Power 6 Light >qlSI Company.

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My commission expires: g]PI/tlf Wt4

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ATTACHMENT Amendment 19 to SHNPP FSAR Description of Revisions by FSAR Section 1.8 (Reg. Guide 1.33) Definition of measurement and test equipment is revised to provide consistency with the CP&L letter to NRC dated October 3, 1984.

1.8 (Reg. Guide 1.55) Hydro testing requirements are revised to eliminate contradictory requirements. These changes require SHNPP to comply with more stringent requirements.

2. 2.3 The amount and location of chlorine stored on site is changed because of unavailability of the original quantity of chlorine planned. The tank car is relocated to comply with Reg.

Guide 1. 95 (also see 6. 4. 4) .

2.5. 6 Berm and ditch dimensions in the figure for the main dam general Fig. 2.5. 6-1 plan are revised to reflect as-built design (also see 3. 7.3, 3.8. 4) ~

2.5. 6 Rockfill and random rockfill rip rap description is revised to 2.5D reflect as-built design. Minor editorial"changes have also been included (also see 3.3.1, 3. 7.2, 3.8).

T.3.2.1-1 Classification of the gross failed fuel detector sample cooler is revised to provide consistency with specifications and original non-nuclear safety requirements. Classification of the reactor makeup water pump motors is revised to reflect as-built design and intended use of equipment as non-safety seismic.

T.3.2. 1-1 Fuel pool nozzles are added to the classification table to provide consistency within the FSAR. The nozzles are classified as NNS (see 3.8.3. 6, 9.1.3.3).

3.3.1.2.1 The coefficients for wind velocity variation with height is Fig. 3.3.1 -1; revised to show correct notations (see 2.5. 6, 3. 7.2, 3.8) 3.3.1-2

3. 7.2 Miscellaneous data in tables are revised to reflect current design, in response to Safety Review Question 220.23; and editorial corrections (see also 2.5D, 3.3.1).

3. 7.3.8.1 Spring rates on hangers/restraints are revised to reflect actual design practice for spring rates. Because calculations are not required, the final design analysis will be based on characteristic spring rates. (This item provides supplemental response to draft SER Open Item 267.)

3. 7.3 The time settlement curve is revised to reflect current design (see also 2.5.6, 3.8.4).

(8 74CGL/crs)

3. 8. 1,7, Revisions are made to the Concrete Containment structure figures Misc. Figs. and pressurization test description to reflect as-built design (see 2.5D, 3.3, 3.7.2)

3. 8.2. 4.1, Additional structural analysis and revised figures of the main Misc. Figs. steam and feedwater region of containment was added for clarification and to reflect as-built design.

3.8.2. 6 CPSL's policy in regard to welding waivers as deviations from ASME III Subsection NE are added to this section 3.8.3.6 A description of the fuel pool nozzles'esign classifications (NNS) and testing requirements is provided for clarification (see also 9.1.3.3).

Fig. 3.8.4-35 Main dam spillway sections are revised to show additions to top Fig. 3.8. 4-39 of rock and show the fine filter replaced by transition filter for better compatibility between layers (see also T.3.2.1 -1, 9.1.3.3) ~

3.8.5.3, Corrections to references and editorial revisions are made.

3.8.5.5,

3. 8A,

3. 8B 3.8 Editorial corrections to references are made.'.9.1, Excessive feedwater flow is added to the upset conditions for T.3. 9. 1-1 steam generators to reflect NUREG-1014 steam generator modifications (see T.3.9.3-1 4, 4.1.1, 4. 4, 5.1.0, 5. 4.2, 10. 4).

T.3.9.1-2a, The discussion of load combinations and acceptance criteria for 3.9.3.3.2 the pressurizer safety and relief system (Class 1) is revised to provide clarification of the model and analysis used.

a T.3.9.3-13 A description of the valving is added to the charging pump miniflow design (to protect the SI pumps) (see also 6.3.2).

T.3.9.3-14 Certain valves were deleted to reflect NUREG-1014 steam generator modifications.

3.9. 4, A description of the seismic sleeve assembly for the control rod Fig. 3.9.4-3; drive system is added, and revisions to the coil stack assembly 3.9. 4-4 thermal clearances and the CRDS Performance Assurance Program is provided to reflect current design.

T.3+10.1-1 The boric acid tank level channels are added to the seismic T.3.11.0-1 instrumentation and electrical equipment tables to reflect current design (as-built conditions).

T. 4. 1 ~ 1-1 Thermal and hydraulic design parameters were revised to reflect NUREG-1014 steam generator modifications.

(8 74CGL/crs)

4. 4.1.3 The description of the core flow design basis is revised to xeflect changes in design (coolant flow into the core baxrel-baffle region, rather than leakage from this region, reflecting considerations for effective heat removal).

4. 4.2.2 A discussion of the effects of rod bow penalties on DNBR is added to reflect NRC-approved Mestinghouse evaluation report

( VCAP-8 691) ~

T ~ 4, 4,2-17 Thermal and hydraulic design parameters were revised to reflect T. 4. 4. 2-2 NUREG-1014 steam generator modifications.

Fig. 4. 4.3-1 Figure for reactor coolant system temperature vs. percent power is x'evised to reflect NUREG-1014 steam generator modifications.

4. 4. 4. 2 The core hydraulics discussion is revised to reflect NUREG-1014 steam generator modifications.

T.5.1.0-1 Thermal and hydraulic operating parameters are xevised to T.5. 1. 1-1, reflect NUREG-1014 steam generator modifications.

5. 4.2.5

,T.5. 4. 13-1 Temperature for faulted and non-faulted transient conditions are added to the pressurizer safety valves design parameters to reflect the type of transient condition not delineated previously.

6.2.lan 2 A description of the refueling canal drains is added. A separate normally closed drain is being provided for decontamination wash%own which will discharge into the equipment drain (see 9 1.3-3).

T. 6.2.2-1 Air flow units are revised from CFH to ACFH. The cooling fan T. 6.2.2-4 data (including motor capacity, insulation, enclosure and code T. 6.2.2-5 data) are also revised to reflect current design and updated information from the vendor.

Fige The fine and coarse screens opening sizes on the containment 6.2. 2-9 sump Section "B-B" drawing is revised to indicate actual design values (see also 9.1. 4, 9.2.1) ~

6.2. 4 A statement is added to this section that indicates that transmitters, sensing lines and isolation valves associated with containment vacuum relief sensing are designated as seismic Category I. This provides supplemental response to Open Item No. 65.

T. 6.2. 4-1 Isolation system penetration detail is revised for consistency with flow diagrams (2165-G-299, Rev. 3) and to reflect NUREG-1014 steam generator modif ications.

(8 74CGL/crs)

6.3.2.1 Descriptions of the charging pump miniflow systems are added in 6.3.2.2 response to Part 21 notification. Component interlocks for T. 6.3.2-3 different modes of operation are also provided. This system is added to provide protection of the ECCS under all modes of plant operation (see also 3.9.3) ~

6. 4. 4.2 The location and quantity of chlorine stored onsite is revised T. 6. 4. 4-1 due to unavailability of the quantity originally planned (see also 2.2.3).

6. 4. 6 A statement indicating that operators will be provided with monitors of control room carbon dioxide and oxygen concentrations is deleted to reflect current design. These monitors are not required.

7.3.1 Schematics for the station service water system logic and schematic diagrams are revised to reflect current design.

T. 7. 4.1-1 Boric acid tank level indicators are added to the list of monitoring instruments for safe shutdown to provide consistency with other sections of the FSAR and to reflect current design.

Reactor coolant system pressure indicators, HVAC System, and Battery Amps are also added.

T. 7. 4. 1-2 Data for RCS wide range pressure, HVAC 'System Battery" 1A-SA and 1B-SB Amps, SW isolation valves, various auxiliary feedwater pump valves and main steam PORVs, SIS valves are added.

Indicators for control roora carbon dioxide and oxygen and low head SI to RCS cold leg valve are deleted to provide consistency within the FSAR and reflect current design.

T. 7.5.1+ Boric acid tank level indicators are added to provide consistency with the FSAR and reflect current design. Other eidtorial changes were made to the table (see also 3.10, 3.11).

8.3.1 The 480 volt switchgear overload alarms is deleted because the load alarm cannot readily provide a reliable source of annunciation for small overloads on motor feeders due to the protection provided for motor feeds. Also, the load alarms cannot be coordinated adequately with the trip d'evices and they do not affect circuit breaker on protective relaying operation.

8.3.1.1, The discussion of the RHR inlet line suction valve power sources Fig. 8.3. 1-5 is revised to reflect a supplemental response to DSER Open Itera 50.

8.3.1.3 Additional information on the physical identification of safety related equipment is revised to provide clarification. Also, the discussion on cable ampacity is reworded to clarify the basis for selecting the proper cable ampacity for those cables installed in a cable tray and to indicate that the specified maximum cable depth is calculated rather than physically measured.

(8 74CGL/crs)

9.1.1.3 K ff infor the spent fuel storage racks is revised to indicate tPiat all cases K ff < .95. This change is consistent with the acceptance criteria for the SHNPP fuel storage Criticality Analyses (the SER states that a K zf C .98 would be acceptable should a optimum moderation situation be postulated).

9.1.3.3 A statement is added indicating that although the fuel pool nozzles will be designed as Seismic Category I, they are not required to be NNS (see also 3.8.3) and will be classified as NNS ~

Fig. 9.1. 4-8, Figures for the Spent Fuel Pool Cask Crane are revised to

-10, -11 reflect current design (see also 6.2.2).

9.2.1 9.2.1 loops' Statement indicating that the normal service water, operating loop is selected by the operator is deleted to provide consistency with system design. (The header will feed both

)

9.2. 4.2 The Harris Energy and Environmental Center and the emergency diesel generator jacket cooling water make-up are added to the systems supplied by the Potable and Service Water System. Other miscellaneous changes are made to reflect current design (see T. 11 2. 3-4) .

~

9.3.2.2 The primary sample system sink drains discharge is revised from Fig. 9.3.2-1 emptying into the Floor Drain System to the Equipment Drain System.

9.3.3.2 The description of the containment building drain system is revised to reflect existing design. The leak detection system is now equipped with a flow switch in the drain pipe, rather than a weir.

9. 4.0 A statement indicating that various cooling and heating calculations for the diesel generator and diesel fuel oil transfer 'buildings, RAB steam tunnel, concrete for structure above RAB steam tunnel and the emergency service water intake sructures will use more conservative temperature extremes.

Specific indoor temperatures for these structures were also changed.

T.9. 4. 4-1, Miscellaneous design data for turbine building structures have 4 -5 been revised to reflect current design.

-6

9. 4.5, Reference to Computer Room humidifier is eliminated and Fig. 9. 4.5-1 Figure 9. 4.5-1 is revised to add smoke purge to the switchgear Room, eliminate reference to dedicated HVAC for the computer and Communication Rooms and add AH-93. (AH-97 supplies to the Computer Room.)

(874CGL/crs)

9. 4.5, -

References to "fire" are changed to "smoke".

T.9. 4.5-1 Battery Room Exhaust system fans and Smoke Purge System data are revised to reflect current design.

9.5.1 Supervisory system compliance is changed from NFPA No. 26 to NFPA No. 72D to clarify and correct the text.

9.'5. 4 The diesel generator storage tank design temperature is revised to conform with building design criteria and notes to the design data are added to provide consistency with the PSAR and provide clarification.

10.4.6 a The statement that the non-radioactive waste is normally

10. 4.7 discharged to the neutralizing basin is revised for clarification. (Normal discharge will flow to the cooling tower blowdown line after sampling and neutralization.) .The waste can be neutralized in the waste tank or sent to the waste neutralization system. (See 11.2.2. 4)

10. 4. 7 The design bases discussion for the condensate and feedwater systems is revised to reflect NUREG-1014 steam generator modifications.

10. 4.8.2 The description of the steam generator blowdown is revised to provide clarification and consistency with flow and 'logic

'iagrams.

10. 4.9.2 The AFS System Operations discussion is revised to reflect NUREG-1014 steam generation modifications.

11. 4.2 A statement is added indicating that a Process Control Program for the Spent Resin Storage tank will be used to ensure compliance with appropriate Technical Specifications. This is in partial response to DSER Open Item 1 76.

T. 11. 4.1-1, Miscellaneous data on the solid processing system inputs

11. 4.2-1 is revised to reflect Unit 2 cancellation.

11.5.2 Miscellaneous data on radiation monitors is revised to 12.3. 4 reflect current design. Monitor failure is deleted from discussions for alarm annunciation. (Monitor failure will still be annunciated, but it will. not have a control function.) This provides partial response to DSER Open Item 187.

12.5 '.1 The calibration frequency for continuous air monitors and portable air samplers is changed from annually to at least semi-annually in order to conform to Regulatory Guide 8.2.5.

13.1.2.2.3 Control operator license is revised from "SRO" to "RO".

Minor editorial changes are also made.

13.5.2 Revisions to the Emergency Operating Procedures, based on Westinghouse Owners'roup Emergency Response Guidelines.

Rev. 1 is added.

(8 74CGL/crs)

14.2.12.1 ~ 8 References to the PABX backup system (Section C.3) are deleted from the plant telephone PABX test requirements since the SHNPP PABX system backup was not part of the plant design. (There are no requirements for a back-up system.)

14.2.12.1 ~ 60 The description of the ERFXS computer system is revised for clarification.

14.2.12.1. 63 The Boron Recycle System is added to the list of safety-related systems receiving reactor makeup water to provide consistency within the FSAR and to reflect current design. Miscellaneous information on the Primary Makeup Hater System Test Summary is also added to provide clarification.

14.2.12.2. 6 The requirement fox'esting RCS flow with various configurations of RC pumps xunning is replaced with a 3 out of 3 RC pump test. Revision 1 of CQL-SU-21.8 no longer requires various configurations of the test. This Westinghouse position has been approved by the NRC.

15.2. 6 A minor editorial change is made for clarification.

1 6.0 The SHNPP Technical Specifications are deleted from the FSAR, to be issued and updated as a separate document, per NRC requirements.

Fig. 17.2.1-1 The QA organization is updated as indicated in our letter dated November 21, 1981.

( 8 74CGL/crs)