ST-HL-AE-1385, Forwards Response to Draft SER or FSAR Items for Chapters 7 & 13 Re TMI Requirements & Operating Plant Organizations, Including marked-up FSAR Pages to Be Incorporated in Future FSAR Amend.List of Draft SER & FSAR Open Items Provided
| ML20138F626 | |
| Person / Time | |
|---|---|
| Site: | South Texas  |
| Issue date: | 10/21/1985 |
| From: | Wisenburg M HOUSTON LIGHTING & POWER CO. |
| To: | Knighton G Office of Nuclear Reactor Regulation |
| References | |
| CON-#485-893 OL, ST-HL-AE-1385, NUDOCS 8510250304 | |
| Download: ML20138F626 (59) | |
Text
{{#Wiki_filter:, The Light l NE 11ouston 1.ighting & Power 11O. Ilox 1700 ifouston.'li- s77001 (713)228-921I October 21 1985 ST-HL-AE-1385 File No. C9.17 Mr. George W. Knighton, Chief Licensing Branch No. 3 Division of Licensing U. S. Nuclear Regulatory Commission Washington, DC 20555 South Texas Project Units 1 and 2 Docket Nos. STN 50-498, STN 50-499 Responses to DSER/FSAR Items For Chapters 7 and 13 on TMI Recuirements and Operatina Plant Ornanizations
Dear Mr. Knighton:
The attachments enclosed provide STP's response to Draft Safety Evaluation Report (DSER) or Final Safety Analysis Report (FSAR) items. The item numbers listed below correspond to those assigned on STP's internal list of items for completion which includes open and confirmatory DSER items, STP FSAR open items and open NRC questions. This list was given to your Mr. N. Prasad Kadambi on October 8, 1985 by our Mr. M. E. Powell. The attachments include mark-ups of FSAR pages which will be incorporated in a future FSAR amendment unless otherwise noted below. The items which are attached to this letter are: l l Attachment Item No.* Subject 1&2 D 13.1-1, D 13.1-2 Operating Plant Organizations l D 13.1-3, D 13.1-4 D 13.1-5, 1 D 13.1-6, 1&2 D 13.1-7, D 13.1-8 1 D 13.1-9, D 13.1-10 D 13.1-11, D 13.1-12,
- Legend D - DSER Open Item C - DSER Confirmatory Item l t i F - FSAR Open Item Q - FSAR Question Response Item L1/DSER/aai 8510250304 851021 PDR ADOCK 05000498 E PDR
Ilouston Lighting & Power Company ST-HL-AE-1385 File No.: C9.17 Page 2 Attachment Item No.* Subject 1&2 D 13.1-13, Operating Plant Organizations 1 D 13.1-14, (Cont'd) 1&2 D 13.4-1, D 13.5-1, 1 D 13.5-2, D 13.5-3, 1&2 F 13.1-1, F 13.1-2, 1 F 13.1-3, F 13.1-4, F 13.1-5, F 13.1-6, F 13.1-7, F 13.2-1, F 13.2-2, F 13.2-31, F 13.4-1 F 7.0-2, 7.0-3 TMI Requirements F 7.0-4, 1&2 F 7.0-5, 1 F 7.0-6, F 7.0-7, F 7.0-32, 1&2 F 7.0-51, F 7.0-52 If you should have any questions concerning this matter, please contact Mr. Powell at (713) 993-1328. Very truly yours, I . (, M. R. Wis nburg Manager, Nuclear Lic ng MAM/b1 Attachments: See above
- Legend D - DSER Open Item C - DSER Confirmatory Item F - FSAR Open Item Q - FSAR Question Response Item L1/DSER/aai L
ST-HL-AE-1385 Houston Lighting & Power Company File No.: C9.17 Page 3 cc: Hugh L. Thompson, Jr., Director Brian E. Berwick, Esquire Division of Licensing Assistant Attorney Ceneral for Office of Nuclear Reactor Regulation the State of Texas U.S. Nuclear Regulatory Commission P.O. Box 12548, Capitol Station Washington, DC 20555 Austin, TX 78711 Robert D. Martin Lanny A. Sinkin Regional Administrator, Region IV 3022 Porter Street, N.W. #304 Nuclear Regulatory Commission Washington, DC 20008 611 Ryan Plaza Drive, Suite 10C0 Arlington, TX 76011 Oreste R. Firfo, Esquire l Hearing Attorney j N. Prasad Kadambi, Project Manager Office of the Executive Legal Director U.S. Nuclear Regulatory Commission U.S. Nuclear Regulatory Commission 7920 Norfolk Avenue Washington, DC 20555 Bethesda, MD 20814 Charles Bechhoefer, Esquire Claude E. Johnson Chairman, Atomic Safety & Senior Resident Inspector /STP Licensing Board c/o U.S. Nuclear Regulatory U.S. Nuclear Regulatory Commission Commission Washington, DC 20555 P.O. Box 910 Bay City, TX 77414 Dr. James C. Lamb, III 313 Woodhaven Road M.D. Schwarz, Jr., Esquire Chapel Hill, NC 27514 Baker & Botts l One Shell Plaza Judge Frederick J. Shon Houston, TX 77002 Atomic Safety and Licensing Board U.S. Nuclear Regulatory Commission J.R. Newman, Esquire Washington, DC 20555 Newman & Holtzinger, P.C. 1615 L Street, N.W. Mr. Ray Coldstein, Esquire Washington, DC 20036 1001 Vaughn Building 807 Brazos Director, Office of Inspection Austin, TX 78701 and Enforcement U.S. Nuclear Regulatory Commission Citizens for Equitable Utilities, Inc. ' Washington, DC 20555 c/o Ms. Peggy Buchorn Route 1, Box 1684
)
E.R. Brooks /R.L. Range Brazoria, TX 77422 Central Power & Light Company P.O. Box 2121 Docketing & Service Section Corpus Christi, TX 78403 Office of the Secretary U.S. Nuclear Regulatory Commission H.L. Peterson/G. Pokorny Washington, DC 20555 City of Austin (3 Copies) P.O. Box 1088 Austin, TX 78767 Advisory Committee on Reactor Safeguards JU.S. Nuclear Regulatory Commission J.B. Poston/A. vonRosenberg 1717 H Street City Public Service Board Washington, DC 20555 P.O. Box 1771 San Antonio, TX 78296 Revised 9/25/85 a n Ll/DSER/asi f t_
Attachment 1 ST-HL-AE-1385 File No.: G9.17 Page 1 of 9 South Texas Project Units 1 & 2 Docket Nos. STN 50-498, STN 50-499 Responses to DSER/FSAR Items For Chapters 7 and 13 on TMI Requirements and Operating Plant Organizations SER Open Item 13.1-1 Provide current and projected size of offsite staff segments. (13.1.1)
Response
The current and projected size 'of the major departments in the Nuclear Group will be included on FSAR Figures 13.1-2H (Nuclear Training), 13.1-4 (Nuclear Assurance),13.1-3 (Nuclear Group), and 13.1-5 (Environmental Protection). Marked up copies of these figures are provided in Attachment 2. SER Open Item 13.1-2 Provide procedures for how the offsite support organization interfaces with the onsite plant organization. (13.1.1)
Response
HL&P understands that this item is essentially a confirmatory item and that NRC will review the onsite/offsite interfaces during a site visit. A revision will be made to FSAR Section 13.1.1.2.1 to document the existence of procedures to govern critical interfaces between departments. An advance copy of this change is included in Attachment 2 (Page 13.1-5). SER Open Item 13.1-3 Provide corporate responsibility for fire protection, and compliance with branch technical position CMEB 9.5.1.(13.1.1)
Response
A statement will be added to FSAR Section 13.1.1.2.3.1 to address this concern. An advance copy of'this change is included in Attachment 2 (Pag'e 13.1-6). SER Open Item 13.1-4 Provide a commitment to conform to ANSI N18.1-1971, plus resumes or other information (beyond what is now in the FSAR) showing conformance. (13.1.1)- STP.704
Attachment ~1-ST-HL-AE-1385 1 File No.: G9.17 Page 2 of 9
Response
STPEGSiscommittedtoANSIN18.1I1971viathecommitmenttoRG1.8 Revision 1-R documented in FSAR Table 3.12-1. Resumes are provided in the FSAR for key management personnel. FSAR Section 13.1.1.4 has been updated to reflect this commitment. FSAR Table 13.1.-1 provides a synopsis of experience for key supervisory personnel. An updated copy of Table 13.1-1 and FSAR Section 13.1.1.4 are provided in Attachment 2. SER Open Item 13.1-5. Engineering expertise on shift will be provided by upgrading the training and qualifications of the shift supervisor. This is an open item pending commission action. ( 13.1. 2.1) -
Response
A revision to FSAR Section 13.1 will be submitted which describes the Shift Technical Advisor (STA) position. STA training is described in FSAR Section 13.2 (Amendment 51). An~ advance copy of the STA description is included in Attachment 2. (Section 7A.I.A.I.1) This supersedes the plan to upgrade the qualifications of the Shift Supervisor. SER Open Item 13.1-6 Final acceptability of the applicant's plans regarding engineering expertise on shift. (13.1.2.2) Response-See Item 13.1-5 SER Open Item 13.1-7 Compliance with shift crew operating experience guidelines of Generic Letter 84-16.
Response
A statement will be added to FSAR Section 13.1.3.1 that states " Plant operating personnel will meet the experience guidelines specified by Generic Letter 84-16." An advance copy of the changed page is included in Attachment 2 (Page -13.1-28). ' SER Open Item 13.1-8 Current and projected size of onsite staff groups. STP.704- i d 4
Attachment-1 i' ST-HL-AE-1385 File No.:-G9.17 l Page 3 of 9 ! t
Response
l The orsenizational charts in FSAR Chapter 13.1 will be modified to identify the current and projected size of the Nuclear Plant Operations Department. Advance copy of these charts are included.in Attachment 2.
~~~~~ . ..w.. . __SER,Op_en Item 13.1-9 Provide resume for Plant Superintendent.
Respon,se The resume for the Plant Superintendent will be provided in an FSAR l amendment when the position is filled. i SER Open Item 13.1-10 Provide opera' tor license requirement for the Plant Manager and/or Plant Superintendent.
; Response The Plant Manager and/or Plant Superintendent will be qualified in accordance with ANSI N18.1-1971 as described in FSAR Chapter 13.1.2.
SER Open Item 13.1-11 Comitment to conform to ANSI N18.1-1971 (or a more recent standard on
- qualification of nuclear power plant personnel), plus resumes or other
- , information (beyond what is now in the FSAR) supporting conformance.
i
Response
Commitments to ANSI N18.1-1971 have been made in FSAR Table 3.12-1 via
; RG 1.8 Revision 1-R. Also, Chapter 13 commits to Reg Guide 1.8, Rev.
j 1-R. Resumes are available on site for Commission review. A copy of current resumes is being provided to NRC under separate cover. SER Open Item 13.1-12 Provide resume for Radiation Protection General Supervisor showing compliance with Reg Guide 1.8 Rev. 1-R. l Response i See the response to open item 13.1-11. 4 STP.704
Attachment 1 .i ST-HL-AE-1385 File No.: G9.17 4 Page 4 of 9 i SER Open Item 13.1-13 i Identify onsite responsibility for fire protection and compliance.with i Branch Technical Position CMEB 9.5-1. I i Rerpense i A statement will be inse-ted in FSAR Section 13.1.2.2 that states
" Chapter 9.5.1.6, Section 3 identifies the onsite person responsible for
- fire protection." An advance copy of this page is included in j Attachment 2 (Page 13.1-19).
4 SER Open Item 13.1-14 f The applicant submitted the STP Training Program by letter dated April 17, 1985. HL&P is drafting an amendment that will incorporate this program description into FSAR Section 13.2. j Response ; This'was provided in FSAR Amendment 51. SER Open Item 13.4-1 The applicant has committed to supply information on the ISEG in a , future FSAR amendment. (13.4.2.2)
Response
J
- HL&P will form an Independent Safety Evaluation Group approximately 6 months prior to fuel load in unit 1. This group will have a staff j complement of at least a supervisor and 4 engineers on a full time basis 1
prior to fuel load. This group will report to the Manager, Nuclear
- Assurance and will be located onsite.
1 i The principal function of this group will be to examine plant operating characteristics, NRC issuances, and other sources of experience ] information that may indicate areas for improving plant safety. The
! ISEG will independently review reports of plant activities. Where useful improvements can be made, the group will present detailed recommendations to corporate management. The ISEG will not have a role in day-to-day operation and management of STPEGS.
i An advance copy of the changed page is included in Attachment 2 (Page 13.4-1). l 1 STP.704
Attachment 1 ST-HL-AE-1385 File No.: G9.17 Page 5 of 9 SER Open Item 13.5-1 The applicant should provide a position regarding the applicability of ANSI /ANS 3.1-1981 qualification requirements to Preoperational and Initial Startup Test Personnel.
Response
FSAR Section 13.5.2.2 will be revised to state:
"10. Prerequisite and Preoperation Testing Procedures A detailed description of the Prerequisite and Preoperational Testing Program including personnel qualifications is provided in
- FSAR Chapter 14.2."
"11. Initial Startup Testing Procedures Initial Startup Testing Procedures will be written to provide detailed instructions, for the conduct and coordination of the Initial Startup Test Program. Initial Startup Testing personnel who ar performing, reviewing, and evaluating activities related to the Initial Startup Testing Program are qualified to perform such activities through previous experience and/or training. The qualifications of these personnel conform to the requirements , specified in Reg Guide 1.58."
An advance copy of this changed page is included in Attachment 2 (Page 13.5-10). 4 SER Open Item 13.5-2 In the FSAR, the application committed to a program in which activities important to safety are to be conducted in accordance with detailed written and approved procedures meeting Reg Guide 1.33. However, the applicant did not specify that the latest revision of Reg Guide 1.33 Rev. 2, would be used.
Response
4 Paragraph 13.5.1.1 specifies Reg Guide 1.33, Rev 2 will be used, a SER Open Item 13.5-3 i The staff requires additional information to determine that the applicant's program for use of operating and maintenance procedure meets the relevant requirements of 10CFR.34, and is consistent with RG 1.33, Rev 2, and ANSI /ANS 3.2-1978. i STP.704
.. ~ . _ _ _ - _ _ . - - _ . . _ . _ _ . . - -
Attachment 1 . ST-HL-AE-1385 File No.: G9.17 , Page 6 of 9 l [ Response i HL&P has committed to Reg Guide 1.33, Rev 2 as shown in Table 3.12-1 and l ANSI /ANS 3.2-1982 for procedures as described in FSAR Section 13.5.1.3, paragraph 1.e. This should be a confirmatory item as any additional
~
information will be available onsite for Commission review during a site
- visit.
FSAR Open Item 7.0-2 I Provide response to 7A.I.A.1.1. t
; Response !
See SER Open items 13.1-5 and 13.1-6. ;
; I FSAR Open Item 7.0-3 Provide response to 7A.I.A.2.3.
Response
l i Incorporated by Amendment 51. r ! FSAR Open Item 7.0-4 Provide response to 7A.I.A.3.1. i
- Response Incorporated by Amendment 51.
} FSAR Open Item 7.0-5 I Provide response to 7A.I.B.1.2.
. Response See SER Open Item 13.4-1. An advance copy of revised pages 7A.I.B.1.
2-1 and -2 are included in Attachment 2. 1 i j' FSAR Open Item 7.0-6 Provide response to 7A.I.C.7. I i f STP.704
, Attachment 1 ST-HL-AE-1385 File No.: G9.17 Page 7 of 9 _
1
Response
This information was provided in FSAR Amendment 51. FSAR Open Item 7.0-7
- Provide response to Item 7A.I.G.I.
Response
This was provided in FSAR Amendment.51. $ FSAR Open item 7.0-32 Provide , response to 7A.II.B.4. '
Response
This'was provided in Amendment 51. i FSAR Open Items 7.0-51 and 7.0-52 Provide responses to 7A.III.A.1.2 and 7A.III.1.1.
Response
. FSAR Section 7A.S covers the required'information.- An advance copy of l page 7A.III.A.2 which closes these items is included in Attachment 2.
FSAR Open Item 13.1-1 13.1.1.1.1.2
- Design of plant and ancillary documents. An evaluation of total '
engineering progress will be provided later. Response. The FSAR will be' updated. An advance copy of the updated page is in-Attachment 2. (Page 13.1-3) ; i ! FSAR Open Item 13.1-2 , 13.1.1.1.1.6 l Procurement of materials and equipment. This will be provided in a j later amendment. l i f STP.704-
! Attachment 1 1 ST-HL-AE-1385 3
File No.: G9.17 Page 8 of 9 i
Response
This is not required information for an FSAR. The section will be i deleted. An advance copy of the updated page is in Attachment 2 (Page 13.1-3) l FSAR Open Item 13.1-3 Add a table listing personnel requirements per shift during normal and refueling operation.
Response
This information will be in the Technical Specifications per NRC
- requirements. It should not be an FSAR open item and is considered closed.
4 FSAR Open Item 13.1-4 Operating Ger.eral Supervisor: Resume to be provided later.
Response
Item has been superseded by later material in FSAR. ) FSAR Open Item 13.1-5 Qualification of key plant personnel. Plant Superintendent resume to be provided later.
, Response See SER Open Item 13.1-9.
FSAR Open Item 13.1-6 Qualifications of nuclear plant personnel. Resume for Electrical Maintenance Supervisor to be provided later.
Response
Item has been superseded by later material in FSAR. See Open Item
, 12.5-1.
FSAR Open Item 13.1-7 Qualification of key plant personnel. 18C Supervisor resume to be provided later. ? STP.704
Attachment 1 ST-HL-AE-1385' ) File No.: G9.17 Page 9 of 9
Response
This item has been superseded by later material in the FSAR.
'FSAR Open Item 13.2-1 l Simulator Training. A more detailed description of the simulator will be provided in a later amendment.
l Response ; This information was provided in FSAR amendment 51. FSAR Open Item 13.2-2 The onsite training organization will be further describe'd in a later amendment.
Response
! This information was provided in FSAR Amendment 51.
i FSAR Open Item 13.2-31 ! Figure 13.2-1
- Station staff training schedule. Provide figure.
- Response This information was provided in FSAR Amendment 51.
- 1 i
FSAR Open Item 13.4-1 Independent safety evaluation group. Information to be provided in a i later amendment. i
Response
See SER Open Item 13.4-1. 4 i F / ? STP.704 i
. . _ . , _ . . _ . , . . . . , _ _ _ , - _ _ . . _ - _ , _ . . _ , _ _ . - - . ~ ~ . _
Attachment 2 ) ST-HL-AE-1385 File No.: G9.17 L South Texas Project Units 1 & 2 Docket Nos. STN 50-498, STN 50-499 Revised FSAR Pages Associated With Responses to DSER/FSAR Items For Chapters 7 and 13 on TMI Requirements and Operating Plant Organizations I STP.704
1 !'* STP FSAR ATTACHM%[
; E / OF '/& 0W I The ASP is intended for use following an evacuation of the control room only.
l (N No actions from the ASP are anticipated during normal plant operations. The i \. transfer of control from the control room to the ASP is alarmed and indicated in the control room through the ESF Status Monitoring System discussed in Section 7.5.4. Access to the ASP is administrative 1y controlled.
- ' 1 7.4.1.9.2 Transfer Switch Panels
- The six transfer switch panels are
- located in the Electrical Auxiliary Building (EAB) with two of the panels located in each of their associated switchgear rooms on El. 10 ft, 35 ft, and 60 ft. The transfer switches and controls provided on the panels are identi-fied in Table 7.4-2. The equipment layout of the transfer switch panels is shown in Figures 7.4-8 through 7.4-13. The switches and controls provided on
; the transfer switch panels are Class 1E. Electrical and physical separation
. is maintained between the separation groups in accordance with the criteria described in Section 8.3. The transfer switch panels provide control transfer between the control room and the ASP control circuits. In addition, control 41 3
is provided on the transfer switch panels for equipment that requires one time or infrequent control during safe shutdown. Transfer of control from the control room is alarmed and indicated in the control room, through the EST Status Monitoring System discussed in Section 7.5.4. The transfer switch panels are intended for use following an evacuation of the control room only. No actions from the transfer switch panels are anticipated during normal plant operations. Access to the transfer switch panels is administratively con-trolled. ' 7.4.1.9.3 Other Local Control Stations: In addition to the controls and n indicators provided at the ASP and transfer switch panels, the following con- ,
~ c.l1 trols are provided outside the control room: '
. 1. Reactor trip capability is provided at the reactor trip switchgear.
- 2. Start /stop controls and transfer switches for the diesel generators.
located on each diesel generator local panel. [44
- 3. Start /stop controls and transfer switches for-the-essential chillers, t
located on each essential chiller local panel.
- 4. Start /stop controls and transfer switches Essential Cooling Water Intake
; Structure (ECWIS) ventilation fans, located at actor control centers.
- 5. Open/close controls for various valves not requiring ismediate or con-stant control, located at motor control centers. 41
- 6. Disconnect switches for solenoid valves to fail open or closed (depending on application) air operated valves, located at the auxiliary relay cabi-nets.
l 7.4.1.9.4 Communications: Communications are provided between the ASP -._ _ the control room, switchgear rooms, and the Technical Support Center (TSC) via
! the de-powered headset system. Onsite telephone extensions are provided a't * ! the ASP and other auxiliary shutduwn control stqtions. Dedicated telephones are provided between the ASP and de TSC and the Emergency Operations (IO4) and the control room. The .4ommunications systems are further scribed' in ection 9 3 2. g t
6 - ( 7.4-15 ,
. Amendment 4'
- s. .
4 .
\
.....a STP FSAR Appendix 7A 3f ATTACHMENT .2.
bA~ I.A.1.1 SHIFT TECHNICA!. ADVISOR ST.HL AE s R5 PAGE .1 OFV6 Position Each licensee shall provide an on-shif t technical advisor to the shif t super-visor. The shift technical advisor (STA) may serve more than one unit at a
,; multiunit site if qualified to perform the advisor function for the various l units.
i'
, The STA shall have a bachelor's degree or equivalent in a scientific or engi-
. neering discipline and have received specific training in the response and 4lj g analysis of the plant for transients and accidents. The STA shall also
.., receive training in plant design and layout, including the capabilities of instrumentation and controls in the control room. The licensee shall assign
.; nomal duties to the STAS that pertain to the engineering aspects of assuring
', 4 safe operations of the plant, including the review and evaluation of operating
.j '
experience. ****
- t 9, '; Clarification .
q ag - [l- i
- - The letter of October 20, 1979 clarified the short tem STA requirements, d;4 That letter indicated that the STAS must have completed all training by
.d January 1, 1981. This paper confi ms these requirements and requests add-itional information.
{ i, y , . _ . .. ... . .
!l .- , The need for the STA position may be eliminated when the qualifications of the 36 i '-., shif t supervisors and senior operators have been upgraded and the man-machine
!.i interface in the control room has been acceptably upgraded. However, until i' those long-tem improvements are attained, the need for an STA program will
, continue. -
1 .
. The staff has not yet established the detailed elements of the academic and
;i, training requirements of the STA beyond the guidance given in its October 30. .
.. 1979 Iceter. Nor has the staff made a decision on the level of upgrading
{l '* required for licensed operating personnel and the man-machine interface in the control room that would be acceptable for eliminating the need of an STA. I Until these requirements for eliminating the STA position have been estab-lished, the staff continues to require that, in addition to the staffing requirements specified in its July 31, 1980 letter'(as' revised by~ftem I.A.1.3 of this enclosure), an STA be availabic for duty on each operating' shift when a plant is being operated in Modes 1-4 for a PWR and Modes 1-3 for a BWR. At
; gj j' other times, an STA is not required to be on duty. !il ' '.G. *. . .,, Since the October 30, 1979 letter was issued, several efforts have been made * [, , to establish, for the longer term, the minimum level of experience, education. *i6 -
and training for STAS. These efforts include work on the revision to ANS-3.1 4 'T."!. . . ~ , .. . ' . . work by the Insti.tuter of Nuclear Power Operations (INPO), and internal staff
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.y; n . . . s.d.,,g go r t s ., .._ ,g,, n,g7, 9 . ., ,, . p.g , ; .,
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**'1NPO recentily mad'e 'available a document entitled " Nuclear Power Plant Shif t -
M '. L. ' i . " " Technical Advisor--Recomendations for Position Description. Qualifications.
,'j ,
Education and Training." A copy of Revision 0 of this document, dated April
,1 [j. 30, 1980, is attached as Appendix C. -Sections 5 and 6 of the INPO document i ,y N.,.$.. . . .
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v.,,..fjdg.ggg a l,1 ~=. ]i.,~rre, m.u vag.,w,..y.tg[jgyg, g, A, g ,1-1 % * %y@u.Wes,-;. -a Amendment. 40 '.
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' . Appendix 7A _
AT TACHMENT .L d ST.HL.AE. ' M Pane ~4 OF yk t I.A.1.1 (Continued) - 1 . i describe the education, training, and experience requirements for STAS. The NRC staff finds that the descriptions as set forth in Sections 5 and 6 of d Revision 0 to the INPO document are an acceptable approach for the selection 0 and training of personnel to staff the STA positions. (Note: This should not i be interpreted to mean that this is an NRC requirement at this time. The
! intent is to refer to the INP0 document as acceptable for interim guidance for a utility in planning its STA program over the long term (i.e., beyond the January 1, 1981 requirement to have STAS in place in accordance with the qualification requirements specified in the staff's October 30, 1979 letter).)
i -
;1 .
. . , , No later than January 1, 1981, all licensees of operating reactors shall pro- .
i . vide this office with a description of their STA training program and their
!I * ! , plans for requalification training. This description shall indicate the level
-~
; 3 i
of training attained by STAS by January 1, 1981 and demonstrate conformance
- 'f- with the qualification and training re'quirements in the October 30, 1979 let-ter. Applicants for operating licenses shall provide the same information in their application, or amendments thereto, on a sp,,hedule consistent with the 38
, NRC licensing review schedule.
1 .. 1, , No,later than January 1, 1981 .all licensees of operating reactors shall pro-hldl, vide this office with a description of their long-term STA program, including i *, i qualification, selection criteria, training plans, and plans, if any, for the eventual phaseout of the STA program. (Note; The description shall include a
,Jk
{i 1 . comparison of the licensee / applicant program with the above mentioned INPO
! document. This request solicits industry views to assist NRC in establishing f*
long-term iciprovements in the STA program. Applicants for operating licenses {
.j shall provide the same information in their application, or amendments thereto, on a schedule consistent with the NRC licensing review schedule.)
nl STP Response 44 _
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ST.HL.AE O#5 PAGE 4 OF 4. 6, z The STA position at the South Texas Project Electric Generating Station will be filled with engineers assigned to the Nuclear Plant Operations Department. The current plans call for ten (10) ens ineers to be trained to function as STAS on a rotating shift basis. The two (2) primary functions of the STA are: 1.) to maximize plant safety during normal operations by independently observing plant status and advising the shift supervisor of conditions that could compromise plant safety; and j' 2.) to maximize plant safety during transients or accidents by independently
]g, assessing plant conditions and providing technical assistance.necessary
~ *. to mitigate the incident whila minimizing the effects on plant personnel, plant equipment, and the environment. -, . - . - - .
' Candidates for the STA position wi.ll'be considered based upon an acceptable combination of education and experience. Nith respect to the educational I
requirements, candidates will possess a bachelor's degree in a scientific or
; engineering discipline or equivalent. . Candidates for the STA position shall j , possess an overall knowledge of the plant. ~ Necessary training will be
.; provided in accordance with the. guidelines presented by the INPO document
- entitled " Nuclear Power Plant Shift Technical Advisor--Recommendations for Position Description, Qualifications, Education, and Training". On an annual basis, the STAS will be required to successfully complete STA requalification
, , training in order to continue to function as an STA.
A waiver for any portion of the above training and education requirements may
., be granted on a case-by-case basis. Training waivers will be considered when i ~ a candidate has documented accredited college courses or can demonstrate an acceptable level of knowledge through comprehensive examinations in the specific area to be waived. -
- .~.
~
i Individuals not actively performing the STA functions for a period of four (4) j' " months or more will, prior to assuming the responsibilities of the position,
-? complete the annual STA requalification training.
. The long-term program for phase out of the STA program by HL&P has not been
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STP FSAR 3 M'g Appendix 7A 7 ATTACHMENT x
- f. I.B.1.2 INDEPENDENT SAFETY ENGINEERING CROUP ST HL AE /3fF G PAGEc OFF6 ,
Position Each applicant for an operating license shall establish an onsite independent safety engineering group (ISEG) to perform independent reviews of plant oper-L ations. The principal function of the ISEG is to examine plant operating character-istics, NRC issuances, Licensing Information Service advisories, and other appropriate sources of plant design and operating experience information that 1 may indicate areas for improving plant safety. The ISEG is to perform inde-4 pendent review problems, and operational analysis, and aid in the establish , ment of programmatic requirements for plant activities. Where useful im-provements can be achieved, it is expected that this group will develop and present detailed recommendations to corporate management for such things as revised procedures or equipment modifications. Another function of the ISEG is to maintain surveillance of plant operations and maintenance activities to provide independent verification that these act-ivities are performed correctly and that human errors are reduced as far as ' practicable. ISEG will then be in a position to advise utility management on the overall quality and safety of operations. ISEG need not perform detailed audits of plant operations and shall not be responsible for sign-off func-j tional such that it becomes involved in the operating organization. (;2, Clarification 30 y q.3 $ The new ISEG shall not replace the plant operations review committee (PORC) ? and the utility's independent review and audit group as specified by current d staff guidelines (Standard Review Plan, Regulatory Guide 1.33, Standard j Technical Specifications). Rather, it is an additional independent group of a
! minimum of five dedicated, full-time engineers, located onsite, but reporting i offsite to a corporate official who holds a high-level, technically oriented
{ position that is not in the management chain-for power productionr-The -ISEG -- will increase the available technical expertise located onsite and will pro-
, vide continuing, systematic, and independent assessment of plant activities. .-
j Integrating the shift technical advisors (STAS) into the ISEC in some way would be desirable in that it could enhance the group's contact with and J{ knowledge of day-to-day plant operations and provide additional expertise..
; However, the STA on shif t is necessarily a member of the operating staff and l cannot be independent of it. *.- It is expected that the ISEG may interface with the quality assurance (OA) } organization, but preferably should not be an integral part of the QA ~
organization, r, I The functions of the ISEG require daily contact with the operating personnel _. and continued access to plant facilities and records. The ISEG review func-tions can, therefore, best be carried out by a group physically located
- onsite. However, for utilities with multiple sites, tit may be possible to perform portions of the independeM safety asses'sment function in a cen-
~
; . tralized location for all'the uti,11ty's plants. In such cases ~,'an on, site - *
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STP FSAR Appendix 7A ' Q-\ -- ATTACHMff4T .L s ats-ST PAGEHL(_f AE 0F dt. I.B.l.2 (Continued) .- group still is required, butjit may be slightly smaller than would be the case if it were performing the entire independent safety assessment function. Stch cases will be reviewed on a c'ase-by-case basis. At this time, the requirement for establishing an ISEC is b'eing applied only to applicants for operating li-
! censes in accordance with Action Plan item I.B.l.2. The staff intends to review this activity in about a year to determine its effectiveness and to see ;
whether changes are required. Applicability to operating plants will be con- 38 sidered in implementing long-term improvenents in organization and management for operating plants (Actin Plan item I.B.l.1). $I STP Response ~ e == n - - ,m n ; - . a ~ - = - -. .- .u. n>_, im
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ATTACHMENT .1 l ST HL AE /w I PAGE 7 0F v/e
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4 III.A.2 IMPROVING LICENSEE EMERGENCY PREPARE 0 NESS--LONG-TERM Position Each nuclear facility shall upgrade its emergency plans to provide reasonable assurance that adequate protective measures can and will be taken in the event of a radiological emergency. Specific criteria to meet this requirement is delineated in NUREG-0654 (FEMA-REP-1), " Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparation in Support of Nuclear Power Plants." ,
'i Changes to Previous Requirem nts and Guidance The final regulations on emergency planning (45 FR 55401-55413) which become effective on November 3, 1980, require the submittal and implementation of the
.- radiological emergency response plans of licensees and state and local entities within the plume exposure and ingestion emergency planning zones (EPZ) by ! January 2, 1981. NUREG-0654 has been revised to include changes developed from team reviews and comments obtained during the comment period.
'I The revised NUREG-0654 establishes the schedule for installation of meteoro- l logical equipment to meet a prescribed implementation date (also see proposed ,
Revision 1 to Regulatory Guide 1.23). The NRC rule establishes July 1, 1981 ; . as the date when the prompt notification capability is to be functional. *
; Item III.A.1.2 establishes dates when emergency response facilities must be ; functional. !
Clarificaf. ion ! In accordance with Task Action Plan item III.A.1.1, " Upgrade Emergency Prepared-ness," each nuclear power facility was required to Immediat'ely~ upgrade"Its' ~
~
emergency plans with criteria provided October 10, 1979, as revised by NUREG-0654 (FEMA-REP-1, issued for interim use and comment, January 1980). New plans [
., were submitted by January 1,1980, using the October 10, 1979 criteria. i '! Reviews were started on the upgraded plans using NUREG-0654 Concomitant to these actions, amendments were developed to 10 CFR Part 50 and Appendix E to ,
10 CFR Part 50, to provide thu long-term implementation requirements. These new rules were issued in the Federal Register on August 19, 1980, with an t effective date of November 3,1980. The revised. rules delineate requirements for emergency preparedness at nuclear reactor facilities. NUREG-0654 (FEMA-REP-1), " Criteria for Preparation and Evaluation of Radiological- ,
.i Emergency Response Plans and Preparedness in Support of Nuclear Power Plants," .'
provides detailed items to be included in the upgraded emergency plans and, along with the revised rules, provides for meteorological criteria, means for - - providing for a prompt notification to the population,' and the need for emer-g l 9ency response facilities (see Item III. A.1.2). -
~ '
I"Plementation of the new rules levied the requirement for the licensee to - - - provide procedures implementing the upgraded emergency plans to the NRC for . - ; review. Pubitcation of Revision 1 to NUREG-0654 (FEMA-REP-1) which incorporates the many public coements received is expected in October 1980. This i.s the ,' ,'. ',l
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ATTACHMENT 1 ST HL AE / W PAGE F OF @ t document that will be used by NRC and FEMA in their evaluation of emergency plans submitted in accordance with the new NRC rules. HUREG-0654, Revision 1; N'UREG-0696, " Functional Criteria for Emergency Response Facilities;" and the amendments to 10 CFR Part 50 and Appendix E to 10 CFR Part 50 regarding ' emergency preparedness, provide more detailed cri-i teria for emergency plans, design, and functional criteria for emergency response facilities and establishes firm dates for submission of upgraded emergency plans for installation of prompt notification systems. These revised criteria and rules supersede previous Commission guidance for the upgrading of emergency preparedness at nuclear power facilities. i Revision 1 to NUREG-0654, " Criteria for Preparation and Evaluation of Radio-logical Emergency Response Plans and Preparedness in Support of Nuclear Power Plants," provides meteorological criteria to fulfill, in part, the standard
' that " Adequate methods, systems, and equipment for assessing and monitoring actual or potential offsite consequences of a radiological emergency condition are in use" (see 10 CFR $50.47). The position in Appendix 2 to NUREG-0654 outlines four essential elements that can be categorized into three functions:
measurements, assessment, and communications. Proposed Revision 1 to Regulatory Guide 1.23, " Meteorological Measurements Programs in Support of Nuclear Power Plants," has been adopted to provide guidance criteria for the primary meteorological measurements program con-sisting system. backup of a primary system and secondary system (s) where necessary, and a Data collected from these systems are intended for use in the assessment of the offsite consequences of a radiological emergency condition. l Appendix 2 to NUREG-0654 delineates two classes of assessment capabilities to provide emergency input for the evaluation of offsite consequences of a radiological condition. Both classes of capabilities provide input to decisions regarding emergency actions. The Class A capacility should provide informa-tion to determine the necessity for ' notification, sheltering, evacuation, and, 3 during the initial radiological phase of a radiological emergency, making confirmatory measurements. The Class B capability should provide information regarding the placement of supplemental meteorological monitoring equipment, and the need to make additional confirmatory radiological measurements. The
' Class B capability shall identify the areas of contaminated property and foodstuff requiring protective measures and may also provide information to determine the necessity for sheltering and evacuation.
Proposed Revision 1 to Regulatory Guide 1.23 outlines the set of meteorological measurements that should be accessible from a system that can be interrogated; the meteorological data should be presented in the prescribed format. The results of the assessments should be accessible from this system; this informa- . tion should incorporate human-factors engineering in its display to convey the essential team. information to the initial decision makers and subsequent management An integrated system should allow the eventual incorporation of effluent monitoring and radiological monitoring,information with the environmental ' transport to provide direct dose consequence assessments. . i .r. . ,^. ,-
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I, . ATTACHMENT J ST HL AE M5 __PAGE */ OF4% Requirements of the new emergency preparedness rutas under paragraphs 50.47 and 50.54 and the revised Appendix E to Part 50 taken together with NUREG-0654 Revision 1 and NUREG-0696, when approved for issuanct., go beyond the previous i requirements for meteorological programs. .To provide a realistic time frame for implementation, a staged schedule has been established with compensating actions provided for interim measures. - [T~ P k esyc>gs c,
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ATTACHMENT L NM N Oo 'f ST HL AE HJ5 STP FSAR / 3.h L PAGE lo OFub Preoperational radiological monitoring activities have been initiated. l13 13.1.1.1.1.2 Design of Plant and Ancillary Documents - Total engineering progress as of Jerr; , 31. LL was 7-ki percent complete overall. l38
%If a985 91 3 13.1.1.1.1.3 Review of Plant Design Features - Design control and review l24 is performed in accordance with the Quality Assurance Program for STP Units 1 and 2, as discussed in the Quality Assurance Program Description (QAPD) for the Design and Construction Phase of the South Texas Project and Chapter 17 of 38 the FSAR.
13.1.1.1.1.4 Development of Safety Analysis Reports - Overall respon-sibility for preparation of the Final Safety Analysis Report rests with HL&P Nuclear Licensing. Preparation of individual sections was assigned to the l20 cognizant technical groups within B&R or BEC, as appropriate and within Westinghouse for the NSSS system and nuclear fuel design. 122 13.1.1.1.1.5 Review of Material and Component Specifications - All l24 safety-related project specifications are reviewed in accordance with the QAPD for STP Units 1 and 2 and in Chapter 17. 12.1.1.1.1.5 Prrer ---- ;f J a h h .-.2 M i; ::: Er p ~ rri ::: ef - ---*a -> : gi;;:n: fr P " nite ' --4- 77-cM- :.1f 7 "; ,, c :--
- 24 cc 7 1 ;;;.
S 13.1.1.1.1./ Management and Review of Construction Activities - HL&P Construction Management has performed the following management and control activities at the Construction site since change to Bechtel Energy Corporation on December 16, 1982.
- 1. ML&P construction personnel monitor field activities in order to assure that STP's construction is in compliance with design and being accom-p11shed by the most expeditious, economical, and safe means possible.
This monitoring includes (1) random inspection of ongoing construction activities for conformance to specifications, drawings, and procedures and; (2) general review of the security, safety, and environmental 38 programs. Construction management plays an active part in the resolution of any problem identified during field monitoring. The construction or-ganization provides the action, direction, and coordination required by other groups, internal or external to'the Company, for the prompt resolu-tion of these problems.
- 2. The contractor's cost and schedule performance is monitored to keep con-struction management and project management informed of project status.
The construction department evaluates ongoing construction activitics for cost and schedule impacts and actively participates in identifying, se-1ecting, and implementing resolutions to eliminate or reduce the effect of such impacts. 13.1-3 Amendment 38
STP FSAR _= ATTACHMENT 3 ST HL AE-/ W , 13.1.1.1.2 Preoperational Activities: epAGE // OF v?. l l 13.1.1.1.2.1 Development of Human Engineering Design Objectives and ) Design Phase Review of Proposed Control Room Layouts - The human engi-neering concepts and objectives used in the control room design have been 38 provided to the NRC as part of the Detailed Control Room Design Review. 13.1.1.1.2.2 Development and Implementation of Staff and Training Programs - The training programs to be utilized for this facility are described in Section 13.2. This program is being implemented in accordance with the schedule indicated in that section. "-c rait ir cf pr::e...mi su fill -t'-- r^-iti rr 1: ::::: ti, i.ilus yl.c; .- 13.1.1.1.2.3 Development of Plans for the Initial Test Program - The initial plant test program for STP is described in Chapter 14. The infor-mation presented in that chapter is supplemented by the STP Startup Manual and the STP Plant Procedures Manual. These documents provide administrative guid-ance during the initial plant test program and contain instructions and proce- 38 dures which address various test activities. These activities include, but are not limited to, organization, interfaces, test procedure development, review and approval, schedules, document control, calibration of test equip-ment, housekeeping and system cleaning, test conduct, and deficiency reso-lution. Nuclear Plant Operations Department (NPOD) procedures for the STP are uti-lized, as appropriate, by Startup to effect a coordinated transition from the startup phase to the operational phase of the project. l44 13.1.1.1.2.4 Development of Plant Maintenance Programs - Organization of the resident maintenance forces is described in Section 13.1.2, " Operating 1 Organization." The journeyman and apprentice electricians and their helpers report through foremen to the Electrical Maintenance Supervisor. The jour- 13 neyman and apprentice mechanics and their helpers report through foremen to the Mechanical Maintenance Supervisor. The journeyman and apprentice instru-ment and control technicians report through their foremen to the Instrument and Control Supervisor. A 3-year formal apprenticeship program administered by HL&P, or equivalent training, must be completed for an employee to become a journeyman. Gradual expansion of the work force assigned to the STP will provide qualified and experienced maintenance personnel prior to initial fuel loading. The STP maintenance program will enab'le equipment to be maintained in a reli-able condition and satisfy the requirements of the regulatory agencies having jurisdiction. The maintenance of those structures, systems, and components that prevent or mitigate the consequences of postulated accidents that could cause undue risk to the health and safety of the public will be maintained in accordance with the requirements of the HL&P Operations Quality Assurance Program. 13.1-4 Amendment 44
f , gh . STP FSAR h',z Pb;LOF % -- The maintenance staff will be sized to perfom the routine and preventive l13 maintenance work load. The station staff will be supplemented by HL&P central maintenance forces or by non-HL&P contract forces during overhaul and repair of major equipment and systems. Maintenance is performed under the direction of cognizant supervisors and in accordance with accepted work prac-tices and procedures. The scope and frequency of preventive maintenance will be based on past expe-rience with similar equipment and the manufacturer's recommendations. Suit-able records will be kept to establish the maintenance history of major safe-ty-related equipment. Written procedures, orders, and instructions which govern maintenance will include sufficient detail to ensure satisfactory com-pletion of the work, but will not necessarily include detailed step-by-step delineations of basic skills normally possessed by qualified maintenance personnel. Except for emergencies, maintenanc2 work will be preplanned. Routine training meetings will be held to foster safety awareness and quality of workmanship.
*13.1.1.1.3 Technical Support for Operations: - The engineering staffs of the Nuclear Engineering and Construction Department will provide the technical support in the areas of nuclear safety, engineering, fuel, and licensing to 4 support the testing and operation of STP. These engineering staffs are Q described in Section 13.1.1.2. 422.
1 The STP plant chemical staff provides radiochemistry support. Health Physics support is an integral part of the Nuclear Plant Operations staff. l24 If the technical support cannot be provided by HL&P, then a consultant will be 38 retained. 13.1.1.2 Organizational Arrangements. 13.1.1.2.1 General: HL&P, the project manager of STP, is engaged u the production, transmission, distribution, and sale of electric energy for lighting, heating, cooling, and power purposes to residential, commercial, and industrial customers. HL&P's service area is in and around Houston, Texas, and includes approximately 5,600 square miles. HL&P operates electric gener-ating plants with a total net capability of 12,196 MW, as of December 31, 38 1082. The company has experience in the design, construction, startup, testing, operating, and staffing of modern generating facilities. l24 The corporate organization, which provides line responsibility for operation of the company, is shown on Figure 13.1-1. Ultimate responsibility for design, procurement, construction, testing, quality assurance, and operation of STP rests with the Group Vice President, Nuclear reporting to the Chairman of the Board and Chief Executive Officer. The Group Vice Pttsident, Nuclear 44 eg 8 assigns responsibilities to the various HL&P organizations described below. l38 fg - W 13.1.1.2.2 Nuclear Plant Operations: The Vice President, Nuclear Plant 124 Operations, reports to the Group Vice President, Nuclear and is responsible
/g for activities related to operation, maintenance, and training of the nuclear 44 generating stations. The Plant operation organization is described in Section 13.1.2.2.
13.1-5 Amendment 44 l
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respons: 4;/bes of ons:le. and offs;le de. pock <vwds 4 atw- goerclwie. on s h and e& ackN:lie.s, i
a1^CHMENT W' 3
<T HL-AE Mf 5 STP FSAR i{ ') b NGE N OF @
l 13.1.1.2.3 Engineering, Construction and Technical Services 13 13.1.1.2.3.1 Nuclear Engineering and Construction: The Group Vice i President, Nuclear reports to the Chairman of the Board and Chief Executive 44 Officer and is responsible for power plant engineering, construction, and ! operation activities as they relate to HL&P's nuclear power facilities. The 13 in g NuclecP' bro;;u p::ri;;; ; d C;;::xni;; Organization is shown in Figure 13.1-3. I24 ' 13.1.1.2.3.1.1 South Texas Project - The Manager, South Texas Project. N)[6'/i?
;7 is responsible to the Group Vice President Nuclear for the management, coor- l44 dination, scheduling, cost control, engineering, construction and startup of t'.e South Texas Project. The STP Department is shown on Figure 13.1-3. 4 The team members are responsible through the Project Management Team, and l 27 ultimately through the Manager, South Texas Project, for the technical ade-
- quacy of work executed in support of STP. Some members of the Project l Management Team are assigned to the team by various departments within the HL&P organization. These assigned team members also serve as interfaces be- 24 tween their individual line organizations and the Project Management Team to ,
ensure the accomplishment of the project-related work pertinent to their de-l partments. 13.1.1.2.3.1.2 Nuclear Engineering - The General Manager, Nuclear I Engineering, reports to the Group Vice President, Nuclear and is responsible l 44
! for Nuclear Services and Nuclear Fuel. (Refer to Figure 13.1-3). l 27 l
13.1.1.2.3.1.2.1 Nuclear Services - The Manager of the Nuclear Services l 41 l
! Department is responsible to the General Manager, Nuclear Engineering, for 27 3 '
q providing technical support to STP in the analytical and specialized t engineering area. These areas include plant and safety analyses, reliability l 38 analyses, N-stamp, and radioactive waste disposal. I l l
, 13.1.1.2.3.1.2.2 Nuclear Fuel - The Manager, Nuclear Fuel, reports to l41 ;
! the General Manager, Nuclear Engineering. He is responsible for the economic
; analyses, procurement activities, and analytical activities relative to nu- 38 .
] clear fuel. Nuclear Fuel interfaces with the STP management team on fuel ! ], related NSSS and balance-of-plant (BOP) items. i 13.1.1.2.3.1.3 Engineering Assurance - The Manager of the Engineering l27
) Assurance Department is responsible 'to the Group Vice President, Nuclear for l 44 i
reviewing the technical adequancy of the engineering and design for STP. l 24 i l 13.1.1.2.3.1.4 Nuclear Licensing - The Manager of the Nuclear Licensing l 41 ! ] Department is responsible to the Group Vice President, Nuclear for the l 44 ! j development and coordination of nuclear licensing policy for HL&P. He l 19 f provides technical direction to project licensing engine. ors and coordinates 27 I
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the flow of nuclear licensing related information among nuclear groups. l 13.1.1.2.3.2 Nuclear Plant Purchasing - The Manager, Nuclear Plant ; i Purchasing, reports to the Vice President, Purchasing and Services, and is ; l responsible for providing project personnel to the South Texas Project in the 39 ! ) following disciplines: purchasing, material control, and contract adminis- i i tration. f
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SIP FCAR ATTACHMENT ;L ST HL AE M35 PAGE n. OF e/[- 13 .1.1.2.3 .3 Environmental Protection - The Manager, Environmental 24 Protection, reports to the General Manager, Fossil Plant Engineering and is responsible for the areas of environmental licensing, air and water quality. l 27 ecology, water resources and nonradioactive waste handling. He is responsible l 38 for preparation of the Environmental Report and the environmental-related por-tions of the safety analysis report. His responsibility also includes acqui- 15 - sition of all local, state, and federal permits and approvals, exclusive of NRC licensing. The Division Manager, Environmental Planning and Assessment, l 38 is responsible for supervising the above activities. The Environmental 15 Protection Department is represented on the STP Project Management Team. This individual is responsible for project interface with the Environmental 18 3 Protection Department. (Refer to Figure 13.1-5). [15 l 13.1.1.2.4 Nuclear Assurance: The Manager, Nuclear Assurance, reports 48 to the Group Vice President, Nuclear. The Manager, Nuclear Assurance, has the authority and responsibility to identify, initiate, recommend, or provide so-lutions to quality related problems and verify the implementation and effect-iveness of the solutions. This position has the authority to "stop work" for 20 l cause in engineering, design, procuresient, fabrication, construction, and operation phases of the nuclear plant. (Refer to Figure 13.1-4). l44 13.1.1.2.4.1 Proiect Quality Assurance Mananer - During the STP con- l41 struction phase, the Project Quality Assurance Manager reports directly to the 138 Manager, NA, on all matters related to quality assurance and is responsible l48 for providing the programmatic direction, and administering policies, goals, objectives, and methods which are described in the Project Quality Assurance 38 Plan. The Project Quality Assurance Manager has the authority to resolve quality 127 related problems and to verify the implementation and effectiweness of the solutions. He has the authority to "stop work" for cause on any quality-re- 20 lated activity of the South Texas Project. 3-
- 7 p .m cro ,m. . 4 . e s. r.m e t -- g gi; g;i;i- - n t- ggggg 2-fired i; :: upd ted 0;;iivo 17.^. 38 13.1.1.2.4.2 Operations Quality Ansurance Mansrer - The Operations l48 Quality Assurance Manager reports directly to the Manager, NA on all matters I related to Operational Quality Assurance. During the pre-operational testing i and plant operation phases, he is responsible for providing the programmatic 38 direction, and administering policies, goals, objectives, and methods which o re
'- described in the Operations Quality Assurance Plan [Sct. F5% Sed,'re ty.:p 13.1.1.2.4.3 Technical Services General Sunnviors - During the STP l48 construction phase, the Technical Services General Supervisors, reports on all 138 technical and administrative matters directly to the Manager, Nuclear g Assurance.
He is responsible for performing vendor evaluations, surveys, surveillances, and audits for the STP. 38 In regards to STP operation, the functions of this position will be further I defined in an updated Section 17.2. 13.1-7 Amendment 48 A
* ^
OTTACHME"'0 ST HL-Ai 13 lh -
. PAGE r7 Of O The QA Organization during STP operation and the Operations Quality Assurance 38 functions are further described in Chapter 17.2 13.1.1.2./q.4 Safeteam: The Manager of the Safeteam Department reports to l44 the Manager, Nuclear Assurance and is responsible for the investigation of l48 employee concerns.
S 13.1.1.2./ System Enaineeri==: The Vice President System Operations is l41 responsible for contractual activities related to the design and construction in j' of the switchyard. In addition, he is responsible for the design of the interfaces between the switchyard and the plant electrical auniliary systems including the main, unit auxiliary, standby and emergency transformers. The l Manager, Engineering Design and Development, is responsible for the design of switchyard electrical equipment and protection, and the interfaces between the 15 I switchyard and the plant electrical auxiliary system. These include the main, unit auxiliary, standby, and emergency transformers. He is also responsible ' for specifying generator characteristics to ensure proper integration of the unit into the system. (Refer to Figure 13.1-1).
, 13.1.1.3 Qualificat ions . Within EL&P, the person whose job position l 27 I
most closely corresponds to that identified as " engineer-in-charge" as defined l 24 i by ANSI N18.1-1971 is the Group Vice President Nuclear. His resume is l44 provided in Section 13.1.1.4 The education and experience of STP key Project Management and Engineering Team personnel are summarised in Table 13.1-1. 24 l ,,,p e y ru b P '***I
' 13.1.1.4 QualifidtionsofF==t== art == Personnel. Resumes of key rr. do ;15
_ ;:::::::isfinvolved in STP are provided in this section. RL&P i organisational charts are provided as figures at the end of Section 13.1. I 1. Group Vice President, Nuclear 40 gf Name: Jerome B. Goldberg, P.E. l Pormal Education: i 1953 BS, Marine Engineering - U.S. Merchants Marine Academy 1960 MSNE - Massachusetts Institute of Technology 15 i Esperience: ! 1955 - 1964 - Bethlehem Steel l Involved in the building of nuclear warships. 1964 - 1971 - General Dynamics ! During this time Mr. Goldberg became Nuclear Construction l Manager and was responsible for the construction of the i nuclear portion of four subearines at the Quincy, i Massachusetts facility. l 4 1971 - 1975 - Stone & Webster Nuclear Engineer assigned to the Beaver Valley 1 Project. , Became Project Manager of Beaver Valley 1 where he remained l until the project was finished in 1975. l 13.1-8 Assadment 48
((l- I ) l TN S EK / P/ffr2 13/~8 ATTAcument a. ST Hl. AE I395 __PAGE /t OF 46 puo /iba / iou > E srf personne f im Sem ~k b f4 / 8 6p>s/ A/isl-n71) ss dx8,a d d in Ps4A Ja Un E. / 2-/ , Eneriene d ' . s w - ~ ,, < :s Or utn'oa., l
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FTP FSAR ATTACHMENT 2 ~ ST HL AE /3JF PAGE /4 OF 96 ' 1974 - 1976 - General Electric Company Senior Engineer involved in the nuclear design of BWR-6 and retrofit of advanced concepts to earlier product lines. Participated in the development of fuel optimization models. 1976 - 1985 - Cincinnati Cas & Electric Company Manager, Nuclear Services Department - responsible for managing activities in the areas of independent safety engineering, nu-clear systems and reliability analysis and nuclear fuel. Responsible for organizing and overseeing the review and eval-ustion of design and engineering changes, station operating procedures, emergency procedures and the nuclear safety aspects of plant performance. Responsible for the generic licensing issues through the BWR Owners Group. Direct the development of in-house capability in the areas of safety analysis, reliabi-lity analysis, and probabilistic risk assessment. Direct all aspects of nuclear fuel supply and fuel management. Managed nuclear training until July, 1983. Manager, Nuclear Fuel and Advanced Engineering Projects - responsible for managing activities in the areas of nuclear fuel, nuclear systems, TMI action plan coordination, generation planning, special corporate studies, and R&D coordination. Special corporate studies included load management evaluations, fuel planning (coal, oil, and nuclear), coal inventory model, and evaluations of various corporate alternatives with finan-44
., o I cial model. Testified as the. Company's wirtnce at hearings of jQW pps#/'$ ppe[/Qf the NRC and the Public Service Commission of Kent M}(
Head of Nuclear Fuel Group - responsibilities included nuclear fuel procurement, contract management, economic analysis, enre j management, and fuel performance. Directed a corporate project V on the marginal costs of electric supply in response to an d [gr rder of the Public Utilities Cosmission of Ohio.
- 7. General Manager Nuclear Engineering Namet C. G. Robertson, P.E.
Formal Education: 1958 BS - U.S. Military Academy. West Point 1965 MSNE - Massachusetts Institute of Technology 1967 NENE - Massachusetts Institute of Technology 19 Experience: 1958 - 1963 - U.S. Army Artillery Corps 1966 - 1973 - General Electric Company (KAPL Division) Performed safety analyses and core thermal /nydraulic I analyses on the reactors for the Nimitz class attack carriers. 13.1-13 Amendment 44 l
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F L l STP FSAR j E hd 1982 - 1984 - Public Service Co. of New Hampshire 3 Seabrook Station Unit #1 (1200 M.W.) assigned as Test Group f, Manager for overall Phase I the Startup and Test activities of a 1200 M. W. Nuclear Station. ' O Responsibilities include directing initial equipment oper- 4g { ation and startup testing, flushing and testing of all plant piping systems includinz ASME Systems and scheduling of startup activities. Certified Level Tester in accordance - l} with ANSI 45.2.6. . iI
. l 1984 - Present - Houston Lighting & Power Company '
South Texas Project, Startup Manager d 13.1.2 Operating Organization j 1 13.1.2.1 Plant Organization. The general plan for staffing STP has the I 38 organization as shown on Figures 13.1-2A through 13.1-2G.
]:
13.1.2.2 Plant Personnel Responsibilities and Authorities. The func- J tions and responsibilities of various positions at STP, including a specific l38 f succession to responsibility for overall operation of the plant in the event f of absences, incapacitation of personnel, or other emergencies, are described l in this section. Chapter Cl. 5 1- b , Sec h e n 'b, denMes -M emsitt pe rsem respendbif for~ he p rv%+ien . 1 13.1.2.2.1 Plant Management:
.{
PLANT MANAGER E The Plant Manager reports to the Vice President, Nuclear Plant Operations and 1 has responsibility for plant production and production support activities to 38 { ensure the safe, reliable and efficient startup, operations, maintenance and g refueling of the STPEGS. Production responsibilities include operations, p maintenance, technical support, and chemical operations and analysis. Produc- d tion support responsibilities include radiological service, management ser- p vices, outage management, and public relations. He is responsible for adhe- g } rence to all requirements of the Operating License and the Technical Specifications. c e. [ PLANT SUPERINTENDENT ]$p i The Plant Superintendent reports to the Plant Manager. He is directly respon- [ sible for all plant production activities including operations, maintenance, j technical support, and chemical operations and analysis. He is directly f responsible for the safe, efficient, and reliable operation of the STEPGS in accordance with the requirements of the Operating T.icense and the Technical 38 Specifications. He assumes the authority and responsibility of the Plant f i Manager in his absence unless otherwise delegated. .c j. . M s it a
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O.g s 13.1-19 Amendment 44 ? k.
1 ATTACHMENT 2 (i 1 ST-HL AE / M'T PAGEJ/ 0F4(e STP P.iAR kg# be given nuclear training where necessary to prepare them for their specific f assignments at the plant. Section 13.2 discusses the nuclear training program t for these personnel. ('. 13.1.3.1 Qualification Requirements. The qualification requirements for plant supervisory, operating, technical, and maintenance support personnel at STP meet or exceed the guidance given on personnel qualifications contained in 4ke. w :lt e.)quer:enceRG "e<+~ 1.8 with clarification rwyu;re mesh sf provided in LeHer-24-/4.cf Crenarts. Table 3.12-1. Pfogf aparafenf l51 jo 13.1.3.2 Qualifications df Plant Personnel. Resumes of Nuclear Plant 38 Operations Department managerial personnel are provided in this section. Resumes of additional plant managerial and supervisory personnel are maintained on file at the plant.
- 1. Vice President, Nuclear Plant Operations Name: Jerrold G. Dewease, P.E.
Formal Education: 1960 BSEE - Christian Brothers College Experience: . 1960 - 1968 - Memphis Light, Gas and Water Electrical Engineer and later as Assistant Electrical Main-tenance Supervisor at the T.H. Allen Electric Generating _
; .t.
Station; Mr. Dewease was involved in providing engineering - support and technical guidance to tru electrical maintenance section. 20 1968 - 1971 - Tennessee Valley Authority Instrument Engineer at the Browns Ferry Nuclear Plant. Mr. Dewease initially worked on establishing the instrument 4 program and technical specifications. 1971 - 1974 Assistant Plant. Mr. Engineering Supervisor at the Browns Ferry Nuclear Dewease had supervisory _ responsibility _over-the-Reactor Engineering, Radio-chemistry, Testing and Instrumen-tation and Control groups. In this position, Mr. Dewease supervised and establishment of the initial surveillance program which implemented the technical specifications and participated in the initial startup of units 1 and 2. 1974 - 1977 Quality Assurance (QA) Supervisor at the Browns Ferry Nuclear Plant. Mr. Dewease was responsible for plant QA during the recovery from the March 1975 fire, the restart of units 3. 1 and 2 after the fire and the. initial startup of unit - During 1976, Mr. Dewease became Assistant Plant Superintendent. 2 l 13.1-28 ' Amendment- 51 l n , , e - k i - c,
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Table 13.1-1 MMMIS AIEllggtIBE2 SU$WlIFS vos m taAP MMim RMFnNG M ma6er of Prefensimmis . At elicable Emperiere broutirs Dirvetly mee Title Focatim As of 2/1/85 To Fach BNTrfW MAMMBGDrr J. H. Coldberg Gasp Tice Freeidea. Acisar NDE. PGE 30 ynare (30 Trs. meleer)
/[ 7 NEIFAR FtAlfr 44 (mlATT(IEs J. C. Dnesse Vice President ' ItSFE - 25 years (17 Trs. Relemr) /1 l51 W. B. Kinsey Ptart %er B9E 20 years (20 Trs, nelear) 3[
(Weant) Plant ageruteulent C. L. Parkey Technical Sq9 art agenetaules MDE 11 years (11 Trs. Relear) 4 51 m C J. V. lasch Chailcal operaties and Ar=1ysis R90E 15 years (9 Trs. Mclear) 3 4 ageristnulert .,
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; Inme Title Feratica As of 7/1/85 To Fath ur1748t FIAlff (FIIRAT!GE (Contimed) l D. L. Smith Namesammt Services Meuser M. Mici 18 years (4 yrs. Ex1 car) 4. _ _ . _
51 C. L. Jerwis llemith armi Safety Services Manger - 35 years (23 Trs. Melear) 4 1RK2 EAR seCDEElt1MC 44 C. C. kiertsco Gmers! Wer. IEi. IGE!. m 19 years (19 Yrs. Acteer) 2
' ~ Mclear Bgiwring SOUm TFRAs faMET ,
4 t J. T. meterseier Messer, 57 F 15.NBE 32 yiers (26 Yrs. Inclear) 5 [ U t. J. Martsd Menger, auppset. l IEDE 21 yters (15 Trs. Relear) [- Jesss==o- Spec;.I A15 3p me sts S. M. Dee . Deputy Projatt. Mmuger MI2 17 years (17 Trs. Eclear) / '/[ E. W. Doteca Manager. Agineerus BSE, M9E. NIIA 21 years (19 Yrs. Meleer) 5
- n. Daly start, Mmuner - 35 yws (2s Trs, melear) (. } tn>
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TARI.E 13.1-1 (Continued) EDUCATION AND EXPFRIFNCE SlHM,LRlF,1 FOR KEY HL&P PERSONNEL St'PPORTING STP l i Number of Professionale Applicable Experience Reporting Directly Name Title Edi. cation As of 2/1/85 to Each SOUTH TEXAS PROJECT (Continued) l Ql sg l J. N. Mailey Princip R Engineer Design BEE 13 years (13 Yrs. Nuclear) -I Er
" . " (u-clos '- Principle of Engineer, h..agtsms . ::: QE MA o
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)$ years (PI Yrs. Naclear) ef al M. A. Robinson Principle Engineer Site BSNE, MBA 19 years (19 Yrs. Nuclear) -I al R. R. Hernandez Principle Engineer, Operation BSCE 11 years (10 Yrs. Nuclear) -j Support 48
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l 1 M.:;;;;; 0 G. Q. Roger $ J. .. ..... Construction Manager 95tE se, gr. ::i. 1 '3 gyears(jWYre. Nuclear) f-J. W. Williams :::;r__..pehalPftNS P i ras.% e r- S l 25 years (11 Yrs. Nuclear) /- c3[@ m-r WQ
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A. O. Bill Manager Nuclear Security Division BA-History MA-Human Resource Mgt. 15 years (15 Yrs. Nuclear) 5 oM 71 W Z
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J. G. White ,Principh[ Engineer, BSME, MSME 11 years (11 Yrs. Nuclear) 4 ? )N k N $N . N f
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TABLE 13.1-1 (Continued) EDUCATION A@ EXPPRIFNCE StfMNARIFS FOR ltEY HL&P PERSONNFl. SUPPORTING STP Number of Professionals Applicable Experience Reporting Directly Name Title Education As of 2/1/83 to Each 44 NitCLEAR ASSURANCE
/ J. E. Geiger Manager, NA ES, Industrial 27 years (8 Yrs. Nuclear) h '8 Engineering
/ T. J. Jordan Project BSNE 11 years (9 Trs. Nuclear) 4 QA Manager
/ J. D. Green Operations QA Manager -
22 years (22 Yrs. Nuclear) 2 44
/ W. N. Phillips Manager Safeteam 80 hre toward BSME 20 years (20 Yrs. Nuclear) 2 or C. B. Biggers Technical Servicea cec *pb-BA-Phy s ic s 20 years (15 Yrs. Nuclear) /3 48 0 General Supervisor
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TABE 13.1-1 (Contirtud) MCATICN A10 EMRIENCE SIMWUIS RR KEY LEAP HRSmNEL SLTIUG'DU SIP Ntsrber of Professionals Appliemble Experience Peportirg Directly Name Title FA ration As of 2/1/85 to Ench MIIFAR SERVICES
/ K. K. Oiitkara Manager, duc.lcor- 54tuic e5 BS Physics, 5 mysics, 13 years (13 Yrs. Nuc1 car) 8 m.D.NE I
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$ / M. A. McBurnett Supervising Ebgineer BSNE, MENE 7 years (7 Yrs. Melear) 2 44%
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'/ M. E. Powell Supervising Bigineer, BHE, ENE 7 years (7 Yrs. Nelear) f3 M' 4 Licensing;
' sit BUINEBUIC ASSURA!CE -
4 R. A. Frazar Manager, Bigineer Lng BSW E 16 years (13 Yrs. Melear) 4 5 Assurance j MK>
~ %..$n MIIIAR FUEL MS BS, Physics ENE 15 years (15 Yrs.' pelaar) 3
? Y e T. M. Sobey. Mangper, Nuclear Ibel$ -
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/ W. F. McGuire Manager BSME 13 years 4 J . W. i..L 0; i.;s ".i..... " O "I-i ; ; . "'" ' ' i; ; ;; ' ' I : Fu ' :: ' ' 2 l ~
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/ D. J. Cody Manager Nuclear Training -- 17 years (17 Yrs. Nuclear) 3 g
a J. R. Walker Training Manager Operations Training AA-Mget. BSIT 13 years (13 yrs. Nuclear) [Z N 4 / B. A. Franta Training Manage,r Staff AS-Bus. Ngat. 16 years (16 Yrs. Nuclear) 3 / 9 w Training Division 116 hrs. of 120 g l towards BSBA g i t 48 l' [ l otn> D M -3 O -4 m > y.O 6 I r u A m> g Om i "- l C2
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-I SOUTH TEXAS PROJECT UNITS 142 NUCLEAR PLANT OPERATO.S DEPARTMENT MAINTENANCE OfVISION Fore 131.T Am M$1 2AfiO23 3 _
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p,d ~ STP FSAR ATTACHMENI
- ST-HL AE- HM $
13.4 REVIEW AND AUDIT PAGE of OF (/b HL&P has provided for a review and audit program that meets the requirements of Section 4 of ANS 3.2-1982. This program is part of the overall administra-tive control and quality assurance (QA) program and is described in the Oper-
;. ations Quality Assurance Plan (0QAP). The review and audit program consists of an independent review' program, an onsite review program, and an audit and surveillance program. The procedures that control the audit and review pro-gram, along with the organization units that implement them, are described l27 i
below. 13.4.1 Onsite Review Onsite review activities are performed by the Plant Operations Review Commit-tee (PORC), which is described in Section 6.0 of the Technical Specifications.
. 13.4.2 Independent Review h =
13.4.2.1 Nuclear Safety Review Board. Indqoudcui s= view accivicies are parfa - d by the Welcar Safoty Re.-icu Sema (ii3RB) =1.151. is dessi'uod in Ecetier A n nf cha Technical Soecifications. TA:U E,47-E U N -1 13.4.2.2 Independent Safety Engineering Group (ISEG). -Tho 15EG is des-7' cri'-d ir ?:: tion 0.0 of i.iin Teuiusicai 5pecifiuations c
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13.4.3 Audit Program _.; The Nuclear Safety Review Board is cognizant of audits of activities described e in Chapter 17. The procedures and organization employed to implement the
,l audit program are discussed in Sections 17.2.2.1 and 17.2.2.4 The HIAP QA
'; staff conducts the audit and surveillance program. The plant QA staff con-ducts audits of operational activities, and the Project Services Division of 51 the QA Department conducts design and procurement audits. Audits are schedul-ed in accordance with a written plan to ensure that all safety-related func-
, tions are audited within a 2-year period. Qualification _of auditors, conducts
't of the audit, reporting of the audit, and follow-up of audit deficiency correc-tions are controlled by a written procedure approved by the Manager, QA.
Copies of audit reports are distributed to all members of the NSRB. _ who- . . .-. n .
\, i .
t 9 13.4-1 3 .. , ,.- . , .~, Amen.dment 51_. 1
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STP FSAR ATTACHMENT > ST HL AE rW PAGE fid OF d6 ' 8 f 5. Investigation of all violations of the Technical Specifi ations,
- 1- including the preparation and forwarding of reports cov ing evaluation
;E and recommendations to prevent recurrence, to the Vice resident,' Nuclear l 20 $,,. '
Plant Operations and to the Nuclear Safety Review Boa (NSRB).
~ '
,, 6. Performanceofspeclialreviews, investigations,or nalyses and reports thereon as requested by the Plant Manager or the N RB. 4
; I
- 7. Review of the plant security plan and implement g procedures.
' 38
- 8. Review of the emergency plan and implementin procedures.
. 9. Review of events requiring 24-hour written otification to the NRC.
{ 4 13.4.2 Independent Review 1
. . 13.4.2.1 Nuclear Safety R ie B ard 15 19 .
Independent review activitie r pe fo ed b the S . The committee is i composed of: ' l 38 t
- l. Vice President, Nucle r Engi e in . d Co st etion (chairman) l 20 38
- 2. Manager, Engineerin suranc i
f 3. Manager, Nuclea Servic s - l e
- 4. 24
.' Manager, Nucl r icensin Il S. Manager, Nucle Fu
$ 6. General Manager, N c ar Engineeri
- 7. Manag ali y urance l43 i [
jj Additiona a be ma be dppointed by the chairman. i l 27 4 1 Regular me ing. of the SL are e led by the chairman once per calendar 8_ !* quarter dur g he initi year of facility operation and at least once per
- j six months t e ea ter S cial' eatings are. called by the chairman as he de ne sa y. Regu r etings of the NSRB will commence prior to fuel l8 ing fo ni 1o a at determined by the chairman. Each member of the SRB ill ave design d it rnates who may attend meetings in place of the 38
- ,, regula m . a ti to the chairman, at least three members or their designa d tern tes t present for reviews to be conducted. - -
NSRB' meet gs a decisio 's will be documented by meeting minutes that are l permanen QA r cor s. ~ il;i. - The N shall revi the following:'
'8
!I ; j ':' 1. The safety evaluations for (1)) hhanges to procedures, equipment, o'r - systems, and (2) tests or exp.,riments completed under the provision of' 10CFR50.59, to verify that such actions did not constitute an.unreviewed - N safety question. ,- . - ! jNf .
, /
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l1 GV'w; .i . ; ; _
. 13.4-2 .,- 3,y y . 3 Amendment -41 ~ - .y.;*
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t STP FSAR b .\ ' ATTACHMENT L ' .. ST-HL AE NT 1
- 5. Radioactive Waste Management Procedures PAGE 'M OF $0 .I Procedures for the operation of the Radwaste Processing Systems will, in ~g conjunction with the plant Radiation Protection Procedures, provide for l38 the control, treatment, and management of radioactive wastes on the plant .
site. These procedures will be developed and implemented by the Plant Chemical Operations Section under supervision of the Chemical Operations 38 g Supervisor. .'
- 6. Electr) al and Mechanical Maintenance Procedures 38 ~
Electrical and Mechanical Maintenance Procedures will provide detailed instructions, where applicable, to ensure that electrical and mechanical d work is performed safely, correctly, and in accordance with prescribed radiation protection measures. These procedures will be prepared and e implemented by the Electrical and Mechanical Maintenance Sections under l38 ;.j the supervision of the Electrical Maintenance Supervisor and Mechanical j 13 Maintenance Supervisor respectively. , , t
- 7. Material Control Procedures Information concerning these procedures is presented in Section 17.2.
- 8. Plant Security Procedures h Information concerning these procedures is presented in the South Texas Project Security Procedures 3
../
- 9. Fire Frotection Procedures
- Fire protection procedures will be written to ensure a coordinated effort in preventing, detecting, suppressing, and extinguishing plant fires. :
Included will be: ' '
'a. . Housekeeping practices s
(E i:
- b. General instructions for plant personnel in the event of a fire
[,
- c. Procedures for maintenance, testing, and calibration of the fire '
detection system i
- d. Procedures for using fire water systems, portable fire fighting l equipment and other installed fire suppression systems ]
- e. Classification and methods of combatting fires
- f. Instructions for fighting fires in various plant areas )j Du s FA T~ &%E U 5-/O .2 b}
n;
.I 13.5-10 Amendment 38 1
( 3,( 'l f/O SE RT PA6'E /3,5~-/D $I?s^6A PAGE 4b OF ,Jij
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