ML17346A827

Forwards Procedures Generation Package, in Response to 841205 Request for Addl Info Re Item 1.C.1 & Suppl 1 to NUREG-0737

ML17346A827
Person / Time
Site:	Turkey Point
Issue date:	02/04/1985
From:	Williams J FLORIDA POWER & LIGHT CO.
To:	Varga S Office of Nuclear Reactor Regulation
Shared Package
ML17346A828	List: ML17346A827 ML17346A829
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-1.C.1, TASK-TM L-85-59, NUDOCS 8502080357
Download: ML17346A827 (7)

Text

REGULATORY I ORMATION DISTRIBUTION SYS

.. 0 (RIDS)

ACCESSION NBR;8502080357 'OC ~ DATE: 85/02/04 NOTARIZED:

NO DOCKET FACIL:50-250 Turkey Point Plant< Unit 3i Florida Power and Light C

05000250 50-251 Turkey Point Planti Unit Ai Florida Power and Light C

05000251 AUTH BYNAME AUTHOR AFFILIATION WILLIAMS'~W~

Florida Power L Light Co, RECIP ~ NAME RECIPIENT AFFILIATION VARGA~S ~ AD Operating Reactors Branch 1

SUBJECT:

For wards "Procedures Generation Package~"

in 841205 request for addi info re Item 1 ',1 NUREG 0737 DISTRIBUTION CODE:

AOPSD COPIES RECEIYED:LTR ENCL TITLE:

OR Submittal Emergency Prep Correspondence NOTES; OL: 07/19/72 OL e 0 4/1 ~l/7 3 response to Suppl 1 to SIZE ~, W+l~

05000250 H

05000251 RECIPIENT ID CODE/NAME NRR ORB1 BC McDONALDtD

,01 INTERNAL; IE/DEPER/EPB 06 EG FILE OQ RGN2/DRSS/EPRPB COPIES LTTR ENCL 1

1 1

1 2

2 1

1 1

1 1

1 RECIPIENT ID CODE/NAME NRR ORB 1 LA IE/DEPER/IRB 12 NRR/DS I/RAB RGN2 E

COPIES LTTR ENCL 1

0 1

1 1

1 1

EXTERNAL: LPDR NSIC 03 1

1 1

1 NRC PDR 02 1

1 TOTAL NUMBER OF COPIES REQUIRED:

LTTR 14 ENCL 13

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FLORIDAPOWER & LIGHTCOMPANY February',

1985 L-85-59 Office of Nuclear Reactor Regulation Attention:

Mr. S.

A. Varga, Chief Operating Reactors Branch gl Division of Operating Reactors U.

S.

Nuclear Regulatory Commission Washington, D.

C.

20555

Dear Mr. Varga:

Re: Turkey Point Units 3 and 4

Docket Nos. 50-250 and 50-251 Supplement 1 to NUREG 0737, Item 1.C.1, Procedures Generation Package for Emer enc 0 eratin Procedures By letter dated December 5,

1984, you requested Additional Information on the Procedures Generation Package for Emergency Operating Procedures.

Below, please find that additional information:

ITEM I If the process used to write plant-specific technical guidelines from generic gui del ines res ults in any devi ati ons from or addi tions to the generi c technical guidelines (because of different plant equipment, oper ating characteristics or design) the PGP should:

1) either identify all deviations and additions, or describe the evaluation performed to determine the safety significance of the deviations and identify all safety-significant deviations; and

2) provide the technical justification (i.e.,

engineering evaluation or

analysis, as appropriate) for all deviations that are identified to the NRC.

RESPONSE

1 The generati on of pl ant-speci fic technical guidel ines utilizes generi c guidelines as outlined in the attached PGP, Section 2.2 (Program Description),

Step 2.2.1, 2.2.2 and 3.

The Transition Document referred to in the aforementioned section is designed to detail the information within existing approved plant procedures as to their incorporation within newly formatted plant-specific technical guidelines.

p gP 8502080357 850204 PDR ADOCK 05000250 F

PDR PEOPLE... SERVING PEOPLE

'I This-document will provide identification of plant-specific technical data presently in use and will refine the information transition to the new plant-specific technical guidelines.

0 Mr.. Steven A. Varga Page 2

In addition to the Transition

Document, the PGP has been revised to include a

plant-specific deviation form, which details technical justification for any differences that are generated between plant-specific EOPs and generic guidelines.

This method will provide plant-specific deviations and technical justification and has been derived from guidance presented in INPO document 83-007 EOP procedure generation package guideline.

ITBI 2 Describe how the generic guidelines and background documentation were used to

'dentify characteristics of needed instrumentation (e.g., setpoints; speed of r'esponse; units) and controls (e.g.,

discrete vs.

continuous controls; response requi rements, frequency of use):

a.

If this information is not available from the generic technical guidelines and background documentation, describe the process used to generate this information (e.g.,

from transient and accident analyses) for identifying instrumentation and control characteristics.

This process can be described in either the PGP or in the function and task analysis portion of the Detailed Control Room Design Review Program Plan with appropriate cross-referencing.

b.

For plant-specific deviations from the instrumentation and controls specified in the generic technical guidelines and background documentation, I) either identify all deviations, or describe the evaluation performed to determine the safety significance of the deviations and identify all safety-significant deviations, and 2) provide a technical justification for each deviation identified to the NRC.

These should be submitted in the plant-specific technical guidelines portion of "the PGP along with any technical deviations.

c.

For each instrument and control used to implement the

EOPs, there should be a descri ption of how the characteristics of the needed instrumentation and controls were determined.

These characteristics should be derived from the information and control needs identified in the background documentation of Revision I of the ERG or from plant-specific information.

RESPONSE

2 a.

The process used to identify the characteristics of needed instrumentation and controls has been outlined in the Task Analysis Upgrade Program which satfsfies the Function and Task Analysis requirements in Supplement I to NUREG-0737.

The Westinghouse Rev.

I, Emergency

Response

Guidelines (ERG) and background documentation will be used as the basis for the Turkey Point plant specific task Analysis of control room operator tasks (ERG steps).

From each "ERG Step" all instruments and control requirements will be identified on the Master Information and Control Requirements List as a

portion of the detailed Control Room Design Review Program Plan.

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Nr. Steven A. Varga Page 3

b.

All instrumentation and control deviations wi 11 be identified per response Number One.

c.

This information has been derived from the 'background documentation provided in the Generic Technical Guidelines and will be supplemented by, the Technical Documentation provided in Response Number One.

Should you or your staff have any questions on this information, please contact us.

Very truly yours, J.

W. Williams, Jr.

Group Vice President Nuclear Energy JWW/SAV/js Attachment cc: J.

P. O'Reilly, Region II Harold F. Rei s, Esquire PNS-LI-85-053-1