ML032250407

Revision to EP-PS-111, TSC Lead Engineer

ML032250407
Person / Time
Site:	Susquehanna
Issue date:	07/31/2003
From:	Susquehanna
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
EP-PS-111
Download: ML032250407 (7)

Text

Jul. 31, 2003 zim Page I of 1 MANUAL HARD COPY DISTRIBUTION DOCUMENT TRANSMITTAL 2003-34566 USER INFORMATION:

Name:GERLACH*ROSE M EMPL#:28401 CA#:0363 Address: NUCSA2 Phone#: 254-3194 TRANSMITTAL INFORMATION:

TO:

GERLACH*ROSE M 07/31/2003 LOCATION:

DOCUMENT CONTROL DESK FROM:

NUCLEAR RECORDS DOCUMENT CONTROL CENTER (NUCSA-2)

--THE FOLLOWING CHANGES HAVE-OCCURRED TO THE HARDCOPY OR ELECTRONIC TO YOU:

MANUAL ASSIGNED 111 -

111 -

TSC LEAD ENGINEER REMOVE MANUAL TABLE OF CONTENTS DATE: 07/02/2003

\\.,ADD MANUAL TABLE OF CONTENTS DATE: 07/30/2003 CATEGORY: PROCEDURES TYPE: EP ID:

EP-PS-111 ADD: PCAF 2003-1551 REV: N/A UPDATES FOR HARD COPY MANUALS WILL BE DISTRIBUTED WITHIN 5 DAYS IN ACCORDANCE WITH DEPARTMENT PROCEDURES.

PLEASE MAKE ALL CHANGES AND ACKNOWLEDGE COMPLETE IN YOUR NIMS INBOX UPON RECEIPT OF HARD COPY, FOR ELECTRONIC MANUAL USERS, ELECTRONICALLY REVIEW THE APPROPRIATE DOCUMENTS AND ACKNOWLEDGE COMPLETE IN YOUR NIMS INBOX.

/AYS

~_-

PROCEDURE CHANGE PROCESS FORM

1. PCAF NO. J / 2. PAGE 1 OF -3

3. PROC. NO.

EP-PS-111 REV. 4

4. FORMS REVISED R_

R_

R_, -

R

_ R R

S. PROCEDURE

TITLE TSC Lead Engineer: Emergency Plan Position Specific Instruction

6.

REQUESTED CHANGE PERIODIC REVIEW s

NO 0

YES' INCORPORATE PCAFS

~ NO E YES- #

REVISION El PCAF DELETION E

(CHECKONE ONLY)

7.

SUMMARY

OFI REASON FOR CHANGE Adds a listing for Tabs 11, 12, 13 to the list of supporting information. This joanIdmirnistrative PCAF since

-the actual tabs are already included in the procedure.

/

-w -

E r

Continued;E

8. DETERMINE COMMJTTEE REVIEW REQUIREMENTS (Refer to Section 6.1.4)

/

\\:

PORC REVIEW REQ'D`37 3 4

/ 0 YES

9.

PORC MTG#

BLOCKS 11 THRU 16ARE ON PAGE2 OFfORM

17.

T.C. Dalpiaz I

(3227 1 07/25/2003

18. COMMUNICATION OF CHANGE REQUIRED?

PREPARER e- -ETN DATE NO El YES (TYPE) _

(Print or Type) 19.f

aX;

z L 7v - -SIGNATURE ATTESTS THAT RESPONSIBLE SUPERVISOR HAS CONDUCTED QADR AND TECHNICAL REVIEW UNLESS OTHERWISE 7

1. nDOCUMENTED IN BLOCK 16 OR ATTACHED REVIEW FORMS.

44RE p

elS'O Ra f 'DA~tV:

f CROSS DSCIPLINE REVIEW (IF REQUIRED) HAS BEEN COMPLETED RP IB

-BY SIGNATURE IN BLOCK 16 ORATTACHED REVIEW FORMS.

20.

r A'

71VLFMAP#OVDATE

21. RESPONSIBL APPROVER ENTER N/A IF FUM HAS APPROVAL AUTHORI[Y INITALS' sDATE FORM NDAP-QA-0002-8, Rev. 8, Page 1 of 2 (Electronic Form)

PROCEDURE CHANGE PROCESS FORM

1. PCAFNO.

';3 '/5 i

12. PAGE2OF 3

13. PROC.NO.

EP-PS-111 REV. 4

11. This question documents the outcome of the 50.59 and 72.48 Review required by NDAP-QA-0726. Either 11a, b, c or d must be checked 'YES' and the appropriate form attached or referenced.

a. This change is an Administrative Correction for which 50.59 and 72.48 are not -

YES s

N/A applicable.

b. This change is a change to any surveillance, maintenance or administrative 3 YES D N/A procedure for which 50.59 and 72.48 are not applicable.

c. This change is bounded by a 50.59172.48 Screen/Evaluation, therefore, no new

] YES s

N/A 50.59172.48 Evaluation is required.

Screen/Evaluation No.

d. 50.59 and/or 72.48 are applicable to this change and a 50.59172.48

[

YES 3 NIA Screen/Evaluation is attached.

12. This change is consistent with the FSAR or an FSAR change is required.

3 YES Change Request No.

13. Should this change be reviewed for potential effects on Training Needs or Material?

YES s

NO If YES, enter an Action Item @ NIMS/Action/Gen Work Mech/PICN

14.

Is a Surveillance Procedure Review Checklist required per NDAP-QA-0722?

[

YES s

NO

15. Is a Special, Infrequent or Complex TesttEvolution Analysis Form required per

] YES 3 NO NDAP-QA-0320? (SICTIE form does not need to be attached.)

16. Reviews may be documented below or by attaching Document Review-Forms NDAP-QA-0101-1.

REVIEWED BY WITH DATE REVIEW NO COMMENTS QADR

__X TECHNICAL REVIEW REACTOR ENGINEERING/NUCLEAR FUELS

• IST OFF OPERATIONS NUCLEAR SYSTEMS ENGINEERING X NUCLEAR MODIFICATIONS i

MAINTENANCE HEALTH PHYSICS NUCLEAR TECHNOLOGY CHEMISTRY OTHER 10CFR50.540 iQILLAQ 2

0,?

Required for changes that affect, or have potential for affecting core reactivity, nuclear fuel, core power level indication or impact the thermal power heat balance. (58)

Required for changes to Section Xi Inservice Test Acceptance Criteria.

FORM NDAP-QA-0002-8, Rev. 8, Page 2 of 2 (Electronic Form)

f;h -1 PAGE 35,0F 1 EP-PS-1I 1 Revision 4 Page 3 of 3 SUPPORTING INFORMATION:

Emergency Telephone Instructions Emergency Organization Logkeeping TSC Ubrary Floor Plan for Work Stations Emergency Facility Form Flow Emergency Classification Big Picture Status Emergency Forms o

Emergency Notification Report Anticipated Question Ust Intentionally Blank Core Damnaage Estimate I Core Damaae Estimate lI Fuel Damaae Worksheet

REFERENCES:

TAB:

TAB I TAB2 TAB 3 TAB 4 TAB5 TAB 6 TAB 7 TAB 8

TAB 9 TAB 10 lTab 1 1 Tab 12

-Tab 13 t-.

I-SSES Emergency Plan Calculation #M-RAF-024, Rev. 0 ZCOTTAP Analysis - Post DBA Reactor Building Temperature Issuei NUREG-0654, Planning Standards and Evaluation Criteria NUREG-0731, Guidelines for Utility Management Structure and Technical SEA-ME-096, EWR#M70777, SEA-EE-063, Resources, 1980 Appendix R Study "Post Accident - Reactor Building Temperature Issue' Rev. 0 fPost LOCA DBA Reactor Building Temperatures -

Electrical Heat Loads'

Tab 9 EP-PS-1 1 1-9 ANTICIPATED QUESTION LIST The following questions are Intended to provide an overview of the event that precipitated entry Into the SSES EMERGENCY PLAN. They will be used by managers In the emergency response organization to better understand the situation and answer questions posed by offsite agencies and regulators.

QUESTION #1:

(TECHNICAL SUPPORT COORDINATOR/ENGINEERING SUPPORT SUPERVISOR)

What is the status of all three fission product boundaries? Indicate what data supports each determination;

a.

Fuel cladding

b.

Reactor coolant pressure boundary

c.

Primary containment QUESTION #2:

(TECHNICAL SUPPORT COORDINATORIENGINEERING SUPPORT SUPERVISOR)

For intact barriers, what threats exist to their continued integrity? For degraded barriers, what is the potential for further degradation? Indicate what data supports each determination.

a.

Fuel cladding

b.

Reactor coolant pressure boundary

c.

Primary containment EP-AD-000-404, Revision 5, Page 1 of 3

Tab 9 EP-PS-1 1 1-9 ANTICIPATED QUESTION LIST QUESTION #3:

(TECHNICAL SUPPORT COORDINATORIENGINEERING SUPPORT SUPERVISOR)

a.

How is the core being cooled?

b.

How do you know that the cooling system(s) in service are adequately removing heat from the core?

c.

What backup cooling systems are available?

QUESTION #4:

(TECHNICAL SUPPORT COORDINATORIENGINEERING SUPPORT SUPERVISOR)

a.

How do you know that the core is In a coolable configuration?

b.

What is the current estimate of core damage?

c.

What is the prognosis for further degradation?

QUESTION #5:

(TECH SUPPORT COORDINATOR)

a.

How do you correlate the in-plant radiological data with the in-plant system parameter data to support your understanding of the situation?

b.

What is the status of off-site radiological releases?

EP-AD-000-404, Revision 5, Page 2 of 3

Tab 9 EP-PS-1 1 1-9 ANTICIPATED QUESTION LIST

c.

If releases are occurring:

1)

What is the release path?

2)

Is the release monitored?

3)

Is the release filtered?

4)

What is the potential for increased release levels? When?

5)

What is the potential for termination of the release? Whern

c.

If releases are not currently occurring:

1)

What are the potentially releasable source terms?

2)

What is the status of SBGTS?

QUESTION #6:

(DOSE ASSESSMENT SUPERVISOR/RADIATION PROTECTION COORDINATOR)

a.

If releases are occurring, what are the off-site release consequences?

b.

What is the potential for the release to change and what would be the off-site consequences of the postulated release?

EP-AD-000-404, Revision 5, Page 3 of 3