ML18022A433

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Forwards Addl Comments on Tech Spec Sections 6.4 & 4.6.2.1.b Re Training & Surveillance Requirements for Depressurization & Cooling Sys,Respectively & Figure 6-2.1 Re Corporate Organization.Final Draft Tech Specs Encl
ML18022A433
Person / Time
Site: Harris Duke Energy icon.png
Issue date: 09/29/1986
From: Zimmerman S
CAROLINA POWER & LIGHT CO.
To: Harold Denton
Office of Nuclear Reactor Regulation
References
NLS-86-377, NUDOCS 8610080407
Download: ML18022A433 (14)
v • d • e


Text

REQ TORY INFORMATION DISTRIBU N SYSTEM (RIDS)

ACCESSION NBR: 8b10080407 DOC. DATE: 8b/09/29 NOTAR I ZED: NO DOCKET 0 FACIL: 50-400 Sheav on Harv is Nuclear Power Planti Unit f i Cav olina 05000400 AUTH. MANE AUTHOR AFFILIATION ZINNERNANi S. R. Cav olina PoU)er & Light Co.

REC IP. NAl'lE RECIPIENT AFFILIATION DENTONp H. R. Office of Nuclear Reactov'egulationi Direc tov (post 851125

SUBJECT:

Forwards addi comments on Tech Spec Sections b. 4 & 4. b. 2. f. b v e tv'aining & surveillance requirements fov depressuv ization

& cooling sgsi v espectivelg & Figure b-2. f v e cov pov ate ov ganization. Final dv aft Tech Specs encl.

DISTRIBUTION CGDE: BGOID CGPIES RECEIVED: LTR l ENCL Q SIZE:

TITLE: Licensing Submittal: PSAR/FSAR Amdts & Related Cov'respondence NOTES:Application for pevmit v enewal filed. 05000400 RECIPIENT COPIES RECIPIENT COPIES ID CODE/NANE LTTR ENCL . ID CODE/NANE LTTR ENCL PWR-A EB 1 1 PWR-A, EICSB 2 2 PWR-A FOB 1 1 PWR-A PD2 LA 1 PWR-A PD2 PD 1 1 BUCKLEY> B 01 2 2 PWR-A PSB 1 PWR-A RSB 1 INTERNAL: ADN/LFI'1B 1 0 ELD/HDS1 1 0 IE FILE 1 IE/DEPER/EPB 3b IE/DGAVT/GAB 21 1 f NRR BWR ADTS 1 0 NRR PWR-B ADTS 1 0 NR N. L 1 1 NRR/DHFT/NTB 1 EQ FILE 04 1 1 RQN2 3 3 RN/DDANI/RIB 1 0 EXTERNAL BNL(ANDTS ONLY) f 1 DNB/DSS (ANDTS) 1 1 LPDR 03 NRC PDR 02 1 NSIC 05 1 1 PNL GRUEL' 1 1 TOTAL NUNBER OF COPIES REQUIRED'TTR 30 ENCL 25

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$ ÃQE Carolina Power 8 Light Company SERIAL: NLS-86-377 SEP 29 1986 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.50-000 TECHNICAL SPECIFICATION COMMENTS

Dear Mr. Denton:

Carolina Power dc Light Company submits additional comments on the Shearon Harris Nuclear Power Plant Technical Specifications (TS). Attachment 1 provides two comments (Record Nos. 806 and 807) on the TS as well as justification for each comment. Attachment 2 provides a marked-up copy of four TS pages for the corresponding comments in Attachment 1.

If you have any questions, please contact Mr. Gregg A. Sinders at (919) 836-8168.

Yours very truly, ager Nuclear Licensing Section GAS/pgp (5017GAS)

Attachments cc: Mr. R. A. Benedict Mr. B. C. Buckley (NRC)

Mr. G. F. Maxwell (NRC-SHNPP)

Dr. 3. Nelson Grace (NRC-Rll) 8610080407 860929 PDR ADOCK 05000400 A PDR

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,l 411 Fayettevilte Street ~ P. O. Box 1551 ~ Raleigh, N. C. 27602 to NLS-86-977 Final Draft TS Comments

DPScl C=mmmen<m SHNPP Fxna1 DI-a+%. Technxca1 Spec9.+xcatxuna Recard Number: 806 Camment Type: ERROR LCO Number".6.4 Paae Number: 6-3 5 7 Sectian Number: 6.4 Sc FIG 6-2. 1 Comment."

IN BOTH Tl-lE FI SUPE At!D IN SECTION 6. 4 CHANGE THE TITLE "DIRFCTOR HARRIS TRAININB UNIT" TO "MANAGER HARRIS TRAINING UNIT".

ON PAGES 6-6 AND 6-7 CHANGE THE REFERENCE FSAR AMENDMENTS TO THE FOLLOWINB:

PAGE 1.8-9 <AM. 26)

PAGES 1.8-10. 11, 12, AtdD 13 <AM. 27)

CORPORATE t'IANAGEMENT HAS CHANGED THE T I TLE QF THI S POSITION. NEITHER THE'ERSON HOLDING THE POSITION OR THE DUTIES OF THE POSITION HAVE CHANGED.

THE CHANGES TO THE FSAR AMENDI'IENT NUMBERS IS TO MAKE THE TECH SPECS CONSISTENT WITH THE LATEST FSAR CHANGES.

a DF" 8cl C=u mmmnCm RHNF'F9.nm1 Dr m+C Tmc=An9.c=m1. &pane=@+9.c:mt;9.nnm Record Number: 807 Comment. Type: ERROR LCO Number ." i.06.02.0i Page Number: 31'4 6-ii Section Number: 4.6.2. i.b Comment:

CHANGE "2i50" TO "i500" CHANGE "DXSCHARGE PRESSURE" TO "DlFFGN'N7(AL

"> -'P" TO 70" i f PRESSURE'HANGE THE PREVIOUS VALUES WERE DETERMINED FOR FULL FLOW CONDITIONS. THIS REQUIRED SOME EXTRAPOLATION OF THE ACTUAL ANALYSIS ASBUHPTIONS ON REQUIRED FLOW TO DIFFERENT SYSTEM CONDITIONS. THE EXTRAPOLATION TO CONDITIONS OTHER THAN THOSE USED IN THE ACTUAL ANAYLSIS REQUIRED OVERLY CONSERVATIVE ASSUMPTIONS, RESULTING IN INAPPROPRIATE TESTING CRITERXA. THE VALUES PRESENTED HERE CORRECT THESE DIFFICULTIES BY PROVIDING ACCEPTANCE CRITERIA WHICH ARE MORE DIRECTLY TRACABLE TO THE AllALYTICALASSUMPTIONS.

THE i500 gpm INDICATED FLOW RATE IS THAT ASSUMED IN THE ANALYSIS <FSAR 6.5.2.w.2) AND THE DIFFERENTIAL PRESSURE REQUIPEMENT IS CONSISTENT WITH FLOW TQ THE CONTAINMENT SPRAY HEADERS IF THE CONTAINMENT ITSELF WERE AT 45 prig. THERE HAS BEEN NO CHANGE TQ THE ANALYSIS NQR IN THE SYSTEM'S ABILITY TO MEET ITS REQUIREMENTS. THIS ERROR DEALS SOLELY WITH AN ASSUMPTION HADE BY CPhL IN AN ATTEt'iPT TO PERFORM THE TEST IN A MORE CONVENIENT SYSTEM CONF I GURAT ION.

Attachment 2 to NLS-86-377

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Markup of TS pages reflecting Final Draft Comments

CONTAINMENT SYSTEMS 3l4.6. 2 DEPRESSURIZATION AND COOLING SYSTEMS CONTAINMENT SPRAY SYSTEH LIMITING CONDITION FOR OPERATION 3.6.2.1 Two independent Containment Spray Systems shall be OPERABLE with each Spray System capable of taking suction from the RWST and transferring suction to the containment sump.

APPLICABILITY:, MODES 1, 2, 3, and 4.

ACTION:

With one Containment Spray System inoperable, restore the inoperable Spray System to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />; restore the inoperable Spray System to OPERABLE status within the next 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.. Refer also to Specification 3.6.2.3 Action.

SURVEILLANCE RE UIREHENTS 4.6.2.1 Each Containment Spray System shall be demonstrated OPERABLE:

4 a.. At least once per 31 days by verifying that each valve (manual, power-operated, or automatic) in the flow path that is not locked, sealed, or otherwise secured:in position, is in its correct position;

b. By verifying that, on an

'igcr~ngo, I pressure, indicated recirculation flow of at least

~5~>~ gpm, each pump develops a or equal to ~

J'l0 of greater than psig when tested pursuant to Specification 4.0.5; c; At least once per 18 months during shutdown, by:

l. Verifying that each automatic valve in the flow path actuates to its correct position on a containment spray actuation test signal and
2. Verifying that each spray pump starts automatically on a containment spray actQation test signal.

Verifying that, coincident with an indication of containment spray pump running, each automatic valve from the sump and RWST actuates to its appropriate position following an RWST Lo-Lo test signal.

d. At least once per 5 years by performing an air or smoke flow test through each spray header and verifying each spray nozzle is unobstructed.

SHEARON HARRIS - UNIT 1 3/4 6-11

CORPORATE ORGANI ZATI ON CHAIRMAHIPRESIOEMT At4 CHIEF EXECUTIVE OFFICER SEMOR EXECUTIVE VICE PRESIQEHT SENIOR VICE PRESIOENT SENIOR VICE PRESIOENT tQHAGER CORPCRATE OPERATIONS SUPPORT NUCLEAR GENERATION auA ITY AS~@X MANAGER HICLEAR SAFETY L VICE PRESIDENT OPERATIONS MANAGER l4JCLEAR MANAGER OA SERVICES ENVI~HTALSERVICES TRAINING L TECH SUPPORT PLANT CONSTRUCTION

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I MANAGER MJCLEAR MANAGER MATERIALOUALITY FL6. SECTION YICE PRESICENT NUCLEAR PGIHEERING AHO LICENSING I MANAGER NUCLEAR MANAGEROPERATIONS OrVOC I

I TRAINING SECTION MANAGER HUCLEAR STAFF SUPPORT

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VICE PRESIDENT

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ONSITE NUCLEAR SAFETY HARRIS TRAININGLNIT HARRIS QXLEAR PROJECT HARRIS PLANT I

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PLANT GEHERAL MANAGER GENERAL MANAGER

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96INEERING MANAGER ADMINISTRATION GENERAL MANAGER MILESTONE CO&LETICN LEGEND

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LI%SOF CWICATIOH MANAGER PLANNING 4 AOt1IHISTRATIYECRGAHIZATION CONTROL

tlNhL UNNI ADMINISTPATIVE CONTROLS 6.2.3 ONSITE NUCLEAR SAFETY (ONS UNIT FUNCTION 6.2.3. 1 The ONS Unit shall function to examine unit operating characteristics, NRC issuances, industry advisories, and other sources of unit design and operat-ing experience information, including units of similar design, which may indi-cate areas for improving unit safety. The ONS Unit shall make detailed recom-mendations for revised procedures, equipment modifications, maintenance activ-ities, operations activities, or other means of improving unit safety, to appro-priate levels of management, up to and including the Senior Vice President-Operations Support, if necessary.,

COMPOSITION 6.2.3.2 The ONS Unit shall be composed of at least five, dedicated, full-time engineers located on site. Each shall have a baccalaureate degree in engineer-ing or related science and at least 2 years professional level exper'ience in his field, at least 1 year of which experience shall be in the nuclear field.

RESPONSIBILITIES 6.2.3.3 The ONS Unit shall be responsible for maintaining surveillance of unit activities to provide independent verification" that these activities are performed correctly and that human errors are reduced as, much as practical.

RECORDS 6.2.3.4 Records of activities performed by the ONS Unit shall be prepared, maintained, and forwarded each calendar month to the Manager-Nuclear Safety and Environmental Services.

6.2.4 SHIFT TECHNICAL ADVISOR 6.2.4.1 The Shift Technical Advisor shall provide advisory technical support to the Shift Foreman in the areas of thermal hydraulics, reactor engineering, and plant analysis with regard to the safe operation of the unit. The Shift Technical Advisor shall have a baccalaureate degree or equivalent in a scien-tific or engineering discipline and shall have received specific training in the response and analysis of the unit for transients and accidents, and in unit design and layout, including the capabilities of instrumentation and controls in the control room.

6. 3 UNIT STAFF UALIFICATIONS 6.3.1 Each, member of the unit staff shall meet or exceed the minimum qualifica-tions of the September 1979 draft of ANS 3.1, with the exceptions and alter-natives noted on FSAR pages 1. 8-8 (Am. 20), 1.8-9 (Am. K), 1.8-10 (Am. K),

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"Not responsible for sign-off function.

SHEARON HARRIS " UNIT 1 6-6

ADMINISTRATIVE CONTROLS UNIT STAFF UALIFICATIONS (Continued 2'it Og 1.8-11 (Am. N), 1.8-12 (Am.N), and 1.8-13 (Am.M), for comparable positions, except for the Manager-Environmental and Radiation Control who shall meet or exceed the qualifications of Regulatory Guide 1,8, September 1975. The licensed Operators and Senior Operators shall also meet or exceed the minimum qualifica-tions of the supplemental requirements specified in Sections A and C of Enclo-sure 1 of the March 28, 1980, NRC letter to all licensees.

6.4 TRAINING rgS~a~f4 6.4. 1 A retraining and replacement training program for the unit staff shall be maintained under the direction of the -Harris Training Unit and shall meet or exceed the requirements and recommendations of the September 1979 draft of ARS 3. 1, with the exceptions and alternatives noted on FSAR pages 1.8-8 (Am.20), 1.8-9 (Am@5), 1.8-10 (Am.22), 1.8-11 (Am ), 1.8-12 (Am.3R , and 1.8-13 (AmQ/), and Appendix A of 10 CFR Part 55 and the supplemental require-ments specified in Sections A and C of Enclosure 1 of the March 28, 1980 NRC letter to all licensees, and shall includ familiarization with relevant industry operational experience.

a7 6.5 REVIEW AND AUDIT 6.5.1 SAFETY AND TECHNICAL REVIEWS 6.5.1.1 General Pro ram Control 6.5.1.1.1 A safety and a technical evaluation shall be prepared for each of the following:

a. All procedares and programs required by Specification 6.8, other procedures that affect nuclear safety, and changes thereto;
b. All proposed tests and experiments that are not described in the Final Safety Analysis Report; and
c. All proposed changes or modifications to plant systems or equipment that affect nuclear safety.

6.5. 1.2 Technical Evaluations 6.5.1.2. 1 Technical evaluations will be performed by personnel qualified in the subject matter and will determine the technical adequacy and accuracy of the proposed activity. If interdisciplinary evaluations are required to cover the technical 'scope of an activity, they will be performed.

6.5.1.2.2 Technical review personnel will be identified by the responsible Manager or his designee for a specific activity when the review process begins; 6.5. 1.3 uglified Safet Reviewers 6.5. 1.3.1 The Plant Geheral Manager shall designate those individuals who will be responsible for performing safety reviews described in Specification 6.5. 1.4.

SHEARON HARRIS " UNIT 1 6-7

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