ML20094B188
| ML20094B188 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 08/03/1984 |
| From: | Mittl R Public Service Enterprise Group |
| To: | Schwencer A Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8408060279 | |
| Download: ML20094B188 (170) | |
Text
Pubhc Service Electnc and Gas Company 80 Park Plaza, Newark, NJ 07101/ 201430-8217 MAILING ADDRESS / P.O. Box 570, Newark, NJ 07101 Robert L. Mitti General Manager Nuclear Assurance and Regulation August 3, 1984 Director of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission 7920 Norfolk Avenue Bethesda, Maryland 20814 Attention: Mr. Albert Schwencer, Chief Licensing Branch 2 Division of Licensing Gentlemen:
HOPE CREEK GENERATING STATION DOCKET NO. 50-354 FSAR CHANGES RESULTING FROM QUALITY ASSURANCE BRANCH MEETING JULY 18, 1984, AND LICENSEE QUALIFICATIONS BRANCH MEETING JULY 23, 24, & 25, 1984 Enclosed as Attachment I are responses to the NRC Quality Assurance Branch open items as discussed at the NRC/PSE&G Quality Assurance meeting held July 18, 1984. Also included are the FSAR modifications to Sections 1.8 and 17.2, Table 3.2-1 and the 260 series question / responses which will be incorporated into FSAR Amendment 8.
Enclosed as Attachment II are the modifications to FSAR Chapter 13 and Section 1.10 which were discussed at the NRC/PSE&G Licensee Qualifications Branch meeting held July 23, 24, and 25, 1984. Please note the modifications to ,
FSAR Section 13.4 and Table 13.1-4 will be submitt'ed at a later date.
Should you have any questions or require any additional information, please contact us. (
Very truly yo rs, h
.jg /
R. L. Mittl General Manager - %
8408060279 840003 PDR ADOCK 05000354 Nuclear Assurance and M A PDR Regulation - 22A DJD:bp Attachment I - FSAR Changes Resulting from Quality Assurance Branch Meeting - July 18, 1984 from Licensee t8 188pignt II - FSAR Changes ResultingQualifications Branch Meeting The Ene/fy c -
July 23, 24, and 25, 1984 954912(39)484
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m Director of Nuclear Reactor Regulation 2 8-3-84 C D. H. Wagner (W/ Attach. I& II)
USNRC Licensing Project Manager W. H. Bateman (W/ Attach. I& II)
USNRC Senior Resident Inspector
-J. Spraul (W/ Attach. I )
USNRC Quality Assurance Branch F. Allenspach (W/ Attach. II)
USNRC Licensee Qualifications Branch IO 31 01/02
ATTACHMENT I ,
I FSAR CHANGES RESULTING FROM QUALITY ASSURANCE BRANCH MEETING - JULY 18, 1984 D
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Item 1 Commitments to Regulatory Guides in Section 1.8 need revision as noted below:
- a. Commitment to Regulatory Guide 1.33 needs clarification regarding " event based" vs " functional" emergency procedures,
- b. Commitment to Regulatory Guides 1.29 and 1.64 needs to address the operations phase.
- c. Commitment to Regulatory Guide 1.94 and 1.144 needs to be clarified to show commitment during the operations phase.
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d., First! paragraph of he . commit'm' ent t'o ',Regtriatory ' Guide . ,,' ,
l'.12-3 needs grammatical clarif.lca'. tion. ' Item a .- -
l' clari'ficationunacceptable 'during 'tte 'operat' ions phase. Delete or provide additional- justification. .
! Response
- a. NRC is requested to provide additional information on the basis for this requirement.
- b. Compliance with Regulatory Guide 1.29 during the operations phase is as stated in Section 1.8.1.39 (see Section 1.8.1, Ammendment 6). Section 1.8.1.64 will be revised to more clearly reflect compliance with Regulatory Guide 1.64 during the operations phase.
- c. Compliance with Regulatory Guide 1.94 during the operations phase is as stated in Section 1.8.1.94.
Section 1.8.1.144 will be revised to more clearly reflect compliance with Regulatory Guide 1.144 during the operations phase.
- d. The first paragraph of the commitment to Regulatory Guide 1.123 will be revised to correct a typographical error. In addition, the commitment to Regulatory Guide 1.123 has been revised to supplement ASME Code procurements with Regulatory Guide 1.38, where required to assure safe shipment. ,
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Item 2 The first sentence of the third paragraph of Section 17.2.16 is garbled.
Response
This sentence should read:
I For significant conditions adverse to quality not ,
identified by NQA, such as LERs, NRC/INPO/CMAP findings, NQA is involved in the review of such conditions and provides oversight to assure timely follow-up and close out through monitoring, additing, and commitment verification. ,
This change will be incorporated in Ammendment 8.
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Item 3 The "as applicable" on the third line of page 17.2-29 needs to be deleted or defined.
Response
4 This change (i.e., to delete "as. applicable") will be incorporated in Amendment 8.
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Item 4
" Periodically" in the last paragraph of Section 17.2.18 needs to be defined.
Response
The introduction to Section 17.2 (page 17.2-1) states, in part:
To assess the ef fectiveness of the PSEEG quality assurance program, independent auditors from outside the company periodically audit the program for compliance with 10 CFR
.50, Appendix B, and other regulatory commitments.
Independent audits shall be conducted at least every two years. Reports of such audits are made directly to upper management.
Section 17.2.18? will. also be' revised, in Ammendment .,8 to
- include 1this information.
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Item 5 Response to Q260.12 and FSAR text needs commitment to one year minimum experience in a nuclear QA organization or an acceptable alternative.
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Response
Section 17.2.1.1.4.1 has been revised to include the information requested.
This change will be incorporated in Amendment 8.
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Item 6 Response to Q260.15 which applies Regulatory Guides to ASME Code covered items "following receipt at the station" is unacceptable.
Response
It is felt that the following PSE&G position, as presented to NRC at the 3/15/84 Hope Creek QA Program review meeting, is consistent with good industry practices and hence does not result in a compromise of controls affecting safety.
PSEEG will comply with applicable supplemental ANSI standards during procurement of Section III components to the extent that such ANSI standards are contained in the applicable ASME edition which the supplier has in effect at the time of procurement.. In addition, applicabl.e , , ,
r.e.quirements of Regulat'ory Guide 1.'38 'will be " applied to- '
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ASME Code procurements where necessary'c to ' assure. safe .
shipment. " R'espons'e to Question 260.15 will be . revised .
accordingly. .
It should be noted that NCA-4000,198 3 edition, endorses the 18 criteria of NOA-1,1979 for N, NV, NPT and NA certificate holders for class 1, 2, 3, MC, CS, CB and CC construction. Therefore, elements of the 10 CFR 50, Appendix B program, not currently included in the ASME QA program for suppliers of the above code items, will be l
addressed as each supplier updates the latest edition of the Code, t
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T-Item 7 The sentence of the response to Q260.32 which states "the designation of those activities..." should be incorporated into the FSAR text.
Response
The requested information will be incorporated in Section 17.2.5 and included in Amendment 8.
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Item 8 The response to Q260.50 needs to be revised to clarify that inspection of operating activities are not performed by personnel within the same group as those performing the activity.
Response
The information requested was incorporated in Section 17.2.10 (page 17.2-27) of Amendment 5. In addition, response to Question 260.50 will be corrected to reference 17 .2.10. The latter revision will be included in Amendment 8.
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Item 9 The response to Q260.60 should reference Technical Specification requirements.
Response
Response to Question 260.60 and Section 17.2.11 will be revised to include the requested information. This revision will be included in Amendment 8. ,
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l Item 10 The response to Q260.65 should include the commitment incorporated into FSAR Section 17.2.16 that: "For significant conditions adverse to quality not identified by action requests, such as LERs, and NRC/INPO/CMAP findings, NQ4 is involved in the review of such conditions and provides oversight to assure timely follow-up and close out through monitoring, auditing, and commitment verification."
1 Response l As stated in response to Question 260.65, the information has been included in Section 17.2.16 (page 17.2-32) as part of Amendment 5. In addition, minor revisions to this information, as previously described in response to Item 2, '
will be included in Amendment '8.
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ITEM 11 i The issues below relate to the scope of the operational QA program as described in Tables 3.2-1 and 17.2-1 through 17.2-4.
Response
a (1) Table 3.2-1 Item I.f has been revised to provide the requested information.
a (2) Table 3.2-1 Item XIX.1 has been revised to provide the requested information.
a (3) SRAI (a) and Table 3.2-1 Item XIX has been revised to provide the requested information.
a (4) SRAI (a) and Table 3.2-1 Items V.c.4 and VI.11 have been revised to provide the requested information.
a (5) Table 3.2-1 Item XV.d has been revised to provide this information. SRAI (1) has been revised to indicate that the SPDS is covered by the operatio'nal QA program.
(b) Table 3.2-1 Item XVIII.j has been revised to provide the requested information.
(c) Table 3.2-1, Footnote (57) has been provided in response to this item.
(d) Table 3.2-1. Item XIX.g has been revised to indicate that the unit vent stacks are subject to the pertinent provisions of 10 CFR 50 Appendix B.
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4 Item 12 Page 28 of FSAR Table 1.11-1 should be revised to reflect the response to NRC Questions 260.14, 260.29, and 260.55.
If this does not result in the deletion of page 28 of the table, the response to the questions listed should be revised such that the page can be deleted.
Response
Information contained on page 28 ( Amendment 6), Table 1.11-1 with respect to dif ferences between the FSAR and SRP Sections II-2A1, II-3E4 and II-12.6, will be deleted in its entirety.
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NCGS FSAR
- 6/04 ThaLE 1.11-1 (cont).. -
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Summary FSAR Sectiontel I
.Leecription of Where ser spectfic sar pieceased amentance eriterla Differences
): section 17.2.6 1 11-241 , . .
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' 04 program to inciado coe- on progsaa presently h j
' mitment that the developeont, not. include commitment that control and use of esapeter the dewelephant, contrG1, ard prograce he conducted use of competer code progrees in we-?- with the 04 scogram he condected in accordance and a ripties of how the with the" 04 program.
On program 1 he applied. ,
- - 17.2.6 11-384 me as::_"' --.have omtrent1F Precedores he establie o been 11ehed to assure essere that verified comput cedea he certified far use that ified competer codes and that their ese be tified for see and that l
egocified. Er use he specified.
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Calibraties of this Primary et esed to L
.l ogelpment should be perform calibrat are at I
against standards t least greater ther. t ces-j I an accuracy of at t four racy of the devices bei...
1 l times the r accuracy calibrated.
N I ef the ogs t being cali- l krated , when this la not .
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t anestee the equipment being calibrated will be ,
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HCGS FSAR 1/84 1.8.1.63 Conformance to Reaulatorv Guide 1.63, Revision 2, July 1978: Electric benetration Assemblies in Contatnment Structures for . tant-Water-Cooled Nuclear Power Plants 4
Although Regulatory Guide 1.63 is not applicable to HCGS, per its implementation section, HCGS complies with the design, qualification, construction, installation, and testing requirements of IEEE 317-1976, as modified by Regulatory Guide 1.63, subject to the clarification in Section 8.1.4.12. l l 1.8.1.64 Conformance to Reaulatory Guide 1.64. Revision 2. Juno 1976: Quality Assurance Reautrements for the Destan ou Nuc ear Power Plants Alth;;;'_
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naanlatary c".id:
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- L4 ;hi. eiend;;4 ie .e swdifi J end ini .y.et;d by .rei;ien i 7 c! T;;. .Lv., Ceti: 1.t'. "r'rver, th: :::htt=c* ="a'"==r A b+
aae c --ly eith Scri;ien ; in-in 6 ii .iler;d ch:: Sin; ;f the d--i;r e.; pet d::::: tr by the eri;irrter's r"peruisa- -
See Section 17.2 for further disciission of quality assurance procedures and Section 1.8.2 for the NSSS assessment of this Regulatory Guide.
1.8.1.65 Conformance to Reaulatorv Gu .nspections de 1.65. Revision 0,-
for Reactor October 1973: Materta es and Vessel Closure Studs Regulatory Guide 1.65 is not applicable.
See Section 1.8.2 for the NSSS assessment of this Regulatory Guide. 1 i
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8 1.8-36 Amendment /
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. l tr;&lics to ReouLatorv Guade 1 87 Revus,on 1 June j h
1.3.1.87 '
Gu ,'-stee for 1 :enstruct
,an o' [ Class 4 :omponeits 97 :Ena= lemon ; to M c:
Levated-Temmera '.ure Beac4 ora i
n 594, 5' )5, and i
' ; ec on ;II code ca-as 1592, 1593, I 194 is t
l Regulatory Guide 1.87 is not applicable to NCGS.
i i 1.3.1.38 Conformance to Reoulatorv Guide 1.08. Rev:,sion 1975: colleet ,an Etermaa, and na ,ntenance 2. of Oct :::
nuclear ;;;;r plant M 11tv ===urance neceres 1 i
During the rations phase, NCGS lies with ANSI N45.2.9-1974, as. mod iod and interpreted egulatory Guide 1.88 7 ,
During the construction and startup phases, compliance is subject l
, to the followi pe Ecific changes.4.,4 oaco- ( stw /w,cw .me). Ar+ ,
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The. architect-engineer ' indicates th,et '.tho' original NCGS project,.,
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consitaent, via the Becht'el nuclear' quality assurance manual -
l' 1NOAN), was to ANSI N45.2.9 (Draft 11, Revision 0, January 17, The NOAM was revised to 1972) rather than to ANSI R45.2.9-1974.
i reference the 1974 docusent, as modified and interpreted by the guide, subject to the following specific changes i
. a. ANSI Section 2.1, Ouality Assurance Record System - Add "The l .
the following sentence at the end of this section:
procedures shall include control of records required during completion of the work activity.*
- b. ANSI Section 2.2.2, Bonpermanent Ouelity" Assurance Nonpermanent Records - Revise this section to read:
records are those required to show evidence that an activity was performed in accordance with the applicable requirement but need not be retained for the life of the ites and do not meet the criteria listed in Section 2.2.1.*
- c. ANSI Section 2.2.2, Indes - Nevise this section to esad "The quality assurance records shall be listed ,
in an indes. The indes shall include, as a minimus, record retention times and the location of the records
- within the record system. The indes system used by organisations for the retention of quality assurance 6
1.s-49 Amenesent/
HCGS FSAR 6/84 Although Regulatory Guide 1.122 is not applicable to HCGS, per its implementation section, HCGS complies with it.
For further discussion of seismic design, see Sections 1.7 and 3.10.
1.8.1.123 Conformance of Reaulatory Gutde 1.123 Revision 1. July 1977: Quality Aosurance Reausrements for Control of tuelear Power Procurement of tems and Services for ,
Plan :s 4
NCGS com;$}es with Regulatory Guide 1.123 puring constructionland i I
startup phases, subject to clarifications stated below. During thews % % g c y lien 29f /r o e ations phase, item a clarifica n L c.,[I. dMY mU % i k d,-[ Q *A The architect-engineer indicates that the original HCGS project commitment was to ANSI.N45,2.'13.(Draft October'1973l'rather than,,-
The architect-engineer NOAM has been " . .
to ANSI N4S.2.13-1976.
' revised to reference the 1976 documenti as modified'by the '
Regulatory Gutde, subject to the following specific changes:
Regulatory Guide Section C.2 - This section requires l a.
the application of elements of the ASME B&PV Code,Section III, Divisions I and 2, and Section XI; and ANSI M45.2.13-1976; specifically, those elements not
- covered by the ASME B&PV Code for procurement of ASME
! The architect-engineer B&PV Cod'e items and services.
takes exception to the requirement, and has the following alternate position: .
The application of the ASME B&PV Code requirements above to the procurement of ASME B&PV Code items and services is adequate, based on the f act t. hat ASME B&PV Code represents the composite knowledge and experience that the of a large segment of the nuclear industry, d for ASME R&PV Code is constantly being reevalute ,
adequacy, that addenda are issued frequently, and that, to our knowledge, historical data do not exist that ;
would indicate that the ASME B&PY Code quality i assurance requirements, relative to the procurement of ASME B&PV items and services, are inadequate. ,
- b. Regulatory Guide Section C.2 - This section of theIt lY regulatory position appears to be inconsistent.
l states that the purchase should verify the implementat.,lon of the suppliers corrective action 8
1.0-74 Amendment [
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NCGS FSAR 4/34 ,
Positions C.1.1. 2, C. 2.1. 2, C. 3.1. 2, and Table 1 of Regulattery f
Guide 1.143 require that all material specifications for ,
! pressure-retaining components within the radioactive process l boundary conform to ASME B&pV Code,Section II. In addition, l
they require that piping materials conform to both the ASME and the identical ASTM specification, and they permit substitution of manufacturers' standards, instead of the ASME specification, in
- the case of pump materials. Although Regulatory Guide 1.143 does l l
not esplicitly address in-line process components, sight flow ;
- glasses, Y-strainers, and steam traps procured by the architect- ;
engineer, and the orifice plates and conductivity elements in the l NSSS scope of supply do not have certificates of compliance for [
l the materials specifLed. A1so, the records of shop inspection, i required by Table 1, for th,e Y-strainers and the steam traps are (
not available from the supplier. ;
l
- Nevertheless, the quality assurance measures taken provide the l
reasonable assurance needed to protect the health and safety of ,;
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., ,',. the.public s'd n that o( plant operating personnel. , , , ,
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Position C.I.2.1. requires that the designated high-liquid-level l conditions should actuate' alarms both locally and in the control' ,
room. For all tanks, a high-liquid-level condition actuates an l !
! alarm in the radweste control rood only. There are no local i j alarms since the tank rooms are controlled areas and normally l i
' unmanned.
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' Position C.4.3 requires that process lines should not be less i than 3/4 inch (nominal). The crystallizer concentrates and l slurry waste transfer lines to the extruder / evaporators are 1/2
! inch nominal, in order to maintain acceptable flow velocities to j
! prevent settling in the lines. The fluid flowrates are on the ;
! order of one (1) GPM as shown in Table 11.4-7 and on Figure j II.4-9.
1 1.. 1.144 Conformanco Po Reculatory Guide 1.144, Revtston i t [
5ectember 91 l0 Aud .t sno of Qualttv Assurance Proarams for Nuclear 'ower P ants HCG 5 complies with Regulatory Guide 1.144 vah b C Sd*M
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Tie archit.ect-on er's quality program for safety-related items during the design and construction phases meets the requirements l of ANS! M45.2.12-1977 as modifled and interpreted by Regulatory i
Amendmed l
HCG'S FSAR 4/84 17.2 OUALITY ASSURANCE DURING THE OPERATIONS PHASE Public Service Electric and Gas Company (PSE&G) is responsible for assuring that the operation, maintenance, refueling is and modification of Hope Creek Generating Station (HCGS) accomplished in a manner that protects public health and safety and that is in compliance with applicable regulatory requirements. To carry out this responsibility, PSE4G has ,
developed and implemented a comprehensive quality assurance program that is applicable The to theof description design, the construction, quality assurance and program testing phases.
provided herein parallels the operational quality assurance program currently being implemented at the Salem Generating Station. .
This operational quality as.urance s program is documented This descriptio'n'is maintainedinby' the nuclear department' manual.
The program provides
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. nucle'ar. operations quali.ty assuran'ce .J NOA)'. '
measur,es to assure the cont'rol of activities affecting.the',
safety-related function of structures, systems, and components.
The quality assurance program encompasses fire protection of safety-related areas and other activities enumerated in Regulatory Guide 1.33. A planned monitoring and audit program assures that specified requirements of the operational quality assurance program are met. The program provides coordinated and centralized quality assurance direction, control, and
' documentation, as required by the NRC criteria set forth in 10 CFR 50, Appendia 5. Applicable NRC Regulatory Guides, codes, Ms h s4 d in the
"**#and standards, as well as the policy statements containemanual, are us
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performing activities affecting safety to ptopare appropriate implementing procedures. To assess the effectiveness of the PSE&G quality assurance program, independent auditors from outside the company periodically audit the program for compliance with 10 CFR 50, Appendia B, and other regulatory commitments.
Independent audits shall be conducted at least every two years.
Reports of such audits are made directly to upper management.
DA p licy statements are issued by key management representatives including the Company Board Chairman / President, by the Senior Vice President - Energy Supply and Engineering and by the Vice President - Nuclear and, as such, are mandatory throughout the
- Company.
17.2-1 Amendment /$
4 NdGS FSAR 4/34 l l
The PSE6G policies and. organization structure assure that the manager - quality quality assurance nuclear operations has i sufficient organizational freedom and independence to carry out i his responsibilities. l I
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! 17.2.1.1.4.1. Nuclear Operations Quality Assurance Personnel l o .x. + ,a,s -
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- The manager - NQA and engineers reportiig directly to him must est4 :
have a combination of 6 years of esperi ence in the field of quality assurance and operations. At l east 1 of these 6 years of esperience must be in the overall imple mentation of a nuclear .
power plant quality assurance program.1 A minimum of 1 year and a manimus of 4 of the 4 years o.f esperience may be fulfilled by ;
related technical or academic training. Personnel performina i
. inspections, esaminations, and test,activitiervare certified.as ';
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,. Level I,: Level II,.' Level'III as, appropriate to their
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' as noted.' ' -
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The manager - nuclear operations quality. assurance fulfills the above qualifications with the addition of the following: '
't
! a. Knowledge and esperience in quality assurance, l f
j b. High level of leadership with the ability to command -
the respect and cooperation of company personnel, vendors, and construction forces Initiative and judpent to establish related policies c.
l to attain high achievements and economy of operations.
17.2.1.1.5 Indapendent Review Groups l Three advisory. group are responsible for reviewing and ,
evaluating items related to nuclear safety. The overall responsibilities of these groups are included in the following sections. More detailed descriptions are contained in i Section 13.4.
I i The SORC is an in station advisor group. Composed of key station personnel, its responsibt ities include review of plant 5
- 17.2-5 Amendment /
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vosvad IerM ss Pe**f */ k E *' W Personnel requiring certification are evaluated to establish their qualifications for their respective level and discipline.
Recertification is based upon demonstrated continued proficiency or requalification, if necessary. Personnel requiring certification in accordance with Regulatory Guide 1.58 are limited to NOA personnel who perform inspection and test activities, M members of the Operational Test Group (OTG) who perform post-design modification testing ' "^^ ^ ^~ - ' n e
.se4ebenkea personnel receive a periodic training needs assessment to identify additional supportive training needs as well as to evaluate individual post-training performance. The e assessment period is three years or less. Inspection and test activities not requiring personnel certification per Regulatory Guide 1.58 include Technical Specification surveillances and periodic inspection and test of fire protection equipment. These personnel are qualifLed and retrained in accordance with applicable requirements of Regulatory Guide 1.8.
are' described in
"'their Trainin'g programs, of support!!ng' required' to organizations,lth the quality -
manuals,.which'are, comply y
' assurance program.
The Nuclear Training Center is responsible for the licensed operator training and retraining, in addition to other technical and supervisory training programs, including General Employee Indoctrination, which is required for all personnel having access to the station.
17.2.3 DESIGN CONTROL .
+
The design control program includes activities such as field design engineering, associated computer programs, compatibility of materials, and accessibility for inservice inspection, maintenance, and repair.
During the operations phase, issuance of new drawings and revisions to existing drawings require the implementation of a design change.
The nuclear support division procedures, approved by the l manager - nuclear operations OA, provide implementation guidance
' for the intent of Regulatory Guide 1.64 " Quality Assurance Requirements for the Design of Nuclear Power Plants." Within that division, the nuclear engineering section has the following responsibilities:
r,,v4,4 A v o./,,,E **'d L waw f 44 skm I'TA.e y y .N. 6,b c,,,6/rwswmvs.k , t wudo pw>+.46, Hk a
cerssk h44. mutwd mo 4w w. rea m +~ A vs, mv d e +wsAA ,\M ./.r<sp't w 17.2 p%,s. .. d f14 Amendment /J
The designation Cf those Cetivities requiring detoiled prCcedures \
I is unde by cognisant department h: ads cnd as o Cinitum, complies :
with applicablo requirement 3 Cf Regu1CtCry Guide 1.33.
M GS FSAR 4/84 I c. Provide right of access for source surveillance and I audit by NOA or its agents l;
- d. Provide for required supplier documentation to be submitted to PSE&G or maintained by the supplier, as appropriate
- e. Provide for PSE&G review and approval of critical procedures prior to fabrication, as appropriate.
Procurement documents require suppliers and contractors of other than commercial grade items to provide services or components in i accordance with a quality assurance program that, complies with applicable parts of 10 CFR 50, Appendix 5. The requirement for
- notifying PSE&G of procurement requirements that have not been
. ' met .is . conveyed to the supplier through the ' standard warranty.
. provision' contained'in.each Purchase ~ Order. .In addition, where- .
" ~10 CFR 21 isiimposed,' suppliers are required *to, comply with, .
- applicable report'ing requirements. '
17.2.5 INSTRUCTIONS, PROCEDURES, AND DRAWINGS Organizations engaged in Q- and F-designated activities are teruired to perform these activities in accordance with written ant approved procedures, instructions, or drawings, as appropriate.
Simple routine activities that can be performed by qualified personnel with normal skills do not require a detailed written-*ea-procedure. Complex activities -n require detailed instructions.
l
- th . y i. owG..;d er ' a=M a= th= d==igaetier ef the m ,....;. Lie J,g.6u...A ...er.egec. }
Procedures include, as appropriate, scope, statement of applicability, references, prerequisites, precautions, l
limitations, and checkoff lists of inspection requirements, in addition to the detailed steps required to accomplish the ;
l i activity. Instructions, procedures, and drawings also contain
! acceptance criteria where appropriate.
l The general manager - Hope Creek operations is responsible for assuring that station procedures are prepared, approved, and implemented in compliance with the station administrative procedures. Documents affecting nuclear safety are reviewed by c I 17.2-19 Amendment /
i
4/04 HCGS TSAR for technical the station operations review committee (50RC) content, by NQA for quality ' assurance requirem designee.
The general manager - nuclear support is responsible for issuing specifications, drawings, blueprints, and instruction and technical manuals associated with and Approved 0- and F-designated implemented structures, modifications <
systems, and components.
and design changes are incorporated to these reference documentsM for the life revisions of of thedocuments these station. are periodically issued by the
- general manager - nuclear support to the general manager - Hope Creek operations to periodically assure that only current and approved referenced documents are used at the station.
l
- ' NOA'r'evie's end approv'es station inspection
- w Changes to plan
/ calibration, . maintenance, modificatI5F, gaMd repair.-In' addition, NOA'
'these documents'are also reviewed and approved.is res test procedures, and results of testing.
17.2.6 DOCUMENT CONTROL Instructions, procedures, drawings, and changes thereto are reviewed for inclusion of appropriate quality assurance requirements and are approved by apppropriate levels of management of the PSE6G organisations producing Measures such documents, l
and distributed on a tisely basis Supplier to usingare documents locations.are documents from the uutng location. controlled according to cont I n t ** '"
The following is a generic listing ofadecuments for theoperational phase, sho and ypproval, including changes thereto ,,.o p t e r l h ,
Design specification - nuclearf :;
tr::t, NOA l s.
mJ,4A
- b. Design f - i ;..-;..;, ..c..;...i 6 ,M,..nww e inn.ii.iW e Ne m doendagen.- nuclear depestment suyp Me ps. 1;,4 :p:% , N 9M s.* Amendment 17.2-20 1
e HCGS TSAR 4/34 an,hMy av3 me sh
- c. Procurement documents 4 nuclear department, i purchasing department,3NQA nwk wm
- d. Or :1 i t , :.... ..... ...... i - & A ><. p v r,,u.f (
- 1.'3.- W/ A
- e. O Men frinirterti';; p. eeed-se; - s-...sei-tienegee -
5;: Ce r r' ;:::t ie;.. , i,GE A a.4 p r, u s7.t-tsg{
- f. Maintenance, modification, and calibration procedures for 0- and F-designated station work activities -
Hope Creek operations, NQA
-;: :::1 ::n;,..
- g. Operating procedures - ;:n.._: ;. ..;; - Hope Creek operations, SORC . .
1 .
. FSAR - du !rr f--^r tr:$t ,-- G Mt!I. F I"L'd,
' h.. '
17,2-1/ c
- 1. Maintenance, inspection, and testing instruction -
nucleardepartmen),NOA imp /* M g ges O
- 3. ; 15:tr e--t --:--eur- - m --- ae, t e.$, e
- t. er a- e=;: ;.,...t. - a.:::= +nrt 7t. -3 -
f F it a .d,44A. M pvo=4m - ova som a ,
L- A/ p h.
In addition, NOA involvement in the work activity includes a review of nonsafety-related work orders for proper classification prior to conducting the activity and a review of completed safety-related work orders.
The establishment and maintenance of a document control system for all instructions, procedures, specifications, and drawings received from the nuclear department, or prepared at the station for use in operating, maintaining, refueling, or modifying items and services covered by the quality assurance program, is the responsibility of the general manager - Hope Creek operations.
The administrative procedures manual describes the control of specific documents. Control of station practices is ir.cluded in the administrative procedures and in department directsves authorized by the responsible station department managers.
Measures are established to assure that the administrative procedures and department directives are up-to-date, are properly A
17.2-21 Amendment /
I
-..a
3,, J sr.t-zin
. a. Nu k 9 .Anu J b d - nuok &
4 m.< ~ ta cia,, w9&
m m a r e.ko us namsi 6 L k i n y ,
x ;, J 1,. z-11 e
- e. . tuv6 QJm.a,J m d- W m-uA ,
a >, e Luelo ;s s thirs >J w:nsMn.a. p>v 4 c.na> ni J da-p d A /td ,suvn
'C vi s.a.8 I1,1 'n.1 c,
_Y. . , ys gg ' riv < 6.w se.v wca .- A a % noed w _
. s p d m.~t m m , & m ri6 4 w asy k A 9:
5 =< A A . h W, f,,ts , Npa %/
T r l' M /<
a41 F.5M12- s & ud sa6 4 & eLp W w y k n c.<-- wu% yp%46pithgw Y'*yut M ov % ote l
~
- g. 4 4 "s4 e
m s
s \ *
. . p
f he a d de % , s + % w 4 n m os't d h per i e w f)rvvo%<aQ ,
J Ma. us.a. af tw % cA % w 44 A e %C+fa ** K./
I **.***d -. u- w A T**. A=1 d [M / e sbA C
$*sImyla $ f MHCGSfSAR% CA 9 m f rnvo' lea.. 4/84
- e. Critical test sequence
- f. Acceptance criteria.
including verification of above items, :: :;;11; ,;c ;
Test results;d and reviewed for acceptability by the qualified are documente department representative. System tests performed following 1
modifications to Q- and F-designated systems requite review of '
test procedures and test results by the SORC.,
, p ,
por+ ~ Ur M NQA moteterrns= monitoric.; ...; the conduct of 4.'.. Aeie.. :h;..;; l
[
eseeptance tests to assure compliance with the test procedure.
Test results are reviewed for the following:
s a.- Pr'esentationj of' proper ldodumentiation' ~^
.s ,
s ls ,
- b. Assurance that tests meet objectives
- c. Identification and reporting of unacceptable results and initiation of corrective measures.
17.2.12 CONTROL OF MEASURING AND TEST EQUIPMENT Test equipment, instrumentation, and controls used to monitor and ,
measure activities affecting quality and personnel safety are identified, controlled, and calibrated atWritten specific intervals for procedures by cognizant nuclear department personnel.
meeting these requirements include provisions for:
- a. Specifying calibration frequency
- b. Recording and maintaining calibration records
. c. Controlling and calibrating primary and secondary standards
- d. Determining methods of calibration
- e. Tracing use on safety-related items.
8 17.2-29 Amendment /
F NCGS FSAR 4/84 repair or "use-as-is" are required to be approved Rework orby the of repair ,
responsible engineering representative.
nonconforming material, parts, or components is inspected and/or retested in accordance with specified test and inspection requirements established by the cognizant engineer, based on applicable made, requirements.
l NOA and the nuclear department review nonconformance reports for '
quality problems, including adverse quality trends, and initiate reports to higher management, identifying significant quality problems with recommendations for appropriate action.
17.2.16 CORRECTIVE ACTION Organiz'ations involye'd;.in activities covered by the quality assurance program are' required to maintain corrective' action , ..
- programs commensurate with their., scope. of :. activity.- ' -
Noncompliances with the quality' assurance program identified by NOA are doc,umented and controlled by, issuing an action. request. ,
NOA reviews responses to action requests for adequacy and monitors these action requests through periodic summary and status reports to management.
Responses to action requests are based on the four elements of corrective action, which are:
- a. Identification of cause of deficiency
- b. Action to correct deficiency and results achieved to date
- c. Action taken or to be taken to prevent recurrence
- d. Date when full compliance.was or will be achieved.
N A For significant conditions adverse to uality not identified by N9 45 such as LERs, NRC/INPO/CMAP findings, is involved in the review of such conditions and provides oversight to assure timely follow-up and close out through monitoring, auditing, and commitment verification.
1 .
t Items 3 and 4 are optional for noncompliances that do not have a significant effect on the quality assurance program.
S 17.2-32 Amendment /
1
- d. Indoctrinetion and training
- e. Implementation of operating and test procedures
- f. Calibration of measuring and test equipment
- g. Fire protection
- h. Otner applicable activities delineated in Table 17.2-2.
The audit data.is analyzed and a written report of the results of -
each c.udit is distributed to appropriate management
- 'reipresentatives of the organization (s).I audited, as well. as to e" ot wt affected_ management'. personnel. 7"r-iadicallv.
. ncluded in.ther.teport.is'.a.
NOAfis.
~
statement of QA' program effectiveness.~'
to verify implementation'of the' -
audited bp independent auditor corporate quality assur.ance pr ram. Reports of these audits are directed to appropriate PSE&G anagement personnel.- l at In t em %o y l
l i
I l
5 17.2-35 Amendment /
l . .
.# QUESTION 260.15 The fourth paragraph of FSAR Section 17.2.2 refers to Section 1.8
'for commitments to Regulatory Guides. Section 1.8 primarily addresses Regulatory Guide commitments during design and construction, and the staff review of the FSAR is concernedWith with Regulatory Guide commitments during the operatione phase.
any proposed clarifications or exceptions, provide a commitment in the FSAR to the effect that: "During the operations phase of HCGS, PSE&G commits to comply with the regulatory position in ..." the appropriate issue of the Regulatory Guide listedoron pages 17.1-26 and 17.1-27 (with RGFor 1.33 replacing systems, RG 1.28) and components, NUREG-0800 (Rev. 2 - July'1981).
structures covered by the ASME Boiler and Pressure Vessel Code Section III (Classes 1, 2 and 3), the code QA requirements should be supplemented by the specific guidance addressed in the (2B3) engulatory positions of the applicable Regulatory Guides.
- s. .
,' [ RESPONSE -
- ~ .
Section 17.2.2 lists regulatory guidance applicable to the QA program. This list has'been revised to include Regulatory Guides I 1.116, 1.123, and 1.144. PSEEG will revise section 1.8 to
~
reflect compliance with listed Regulatory Guides which are applicable during the operations phase, along with any clarification, modifications, etc. by June 1984.
The code QA requirements are used for the procurement of systems, components and structures covered by the ASME Boiler and Pressure The standard QA Vessel Code Section III (classes 1, 2, and 3).
program controls apply to 0-Listed code items following receipt l
! at the station. L g'4 /f Q (f gu f l % ul h G'a L 1 3 e u. i t/ he. apped % Asnie c L yacme4- wk su ceam He mva s4 s A,,,4 M
8 260.15-1 Amendmentf (
~d HCGS FSAR 1/84 OUESTION 260.50 (SECTION 17.2)
Describe the provisions which assure that when inspections associated with normal operations of the plant (such as routine maintenance, surveillance, and tests) are performed by individuals other than those who performed or directly supervised the work, but are within the same group, the following controls are met: (SRP Section 17.2.10, item 2)
- n. The quality of the work can be demonstrated through a functional test when the activity involves breaching a pressure retaining item.
- b. The qualification criteria for inspection personnel are reviewed and found acceptable by QANO prior to initiating the inspection.
s
, RESPONSE .
, .. r . . .
~
7 see response' tc'. Questions"260..7 'and' 260.19. - s
- 1 .
has been revised to provide -
Section 17.2JO ' ~
additional information requested _.
l i
l 5
260.50-1 Amendment /
~
llCGS FSAR 4/84 l QUJSTION 260.6C (SECTION 17.2)
Describe those' provisions which assure that procedures are established to control altering the sequence of required Such tests, actions inspections, and other safety-related operations.
should be subject to the same controls as the original review and approval. (14.3)
RESPONSE
Section 17.2.11 states in part:
Test procedures prescribe, as applicables (d) Critical test sequence
..... Test' results are documented and reviewed for acceptability by' the qualified departmentJepresentative.-
,' in addition, station.'adm[nis'trative. procedures . provide for the., '
use 'of teniporary changes. h -
of.temporarychangesare'fDetailinst'ructionsforimplemetation-provided. ,
I Lo [ E M % C M b // c /* Wbw 4t4 T M nicJ S p%&
$ 8.
260.60-1 Amendment [ l
_ _ . _ ~ . - _ - - _ . . _ ~ _ . . .- - - - - - -- ~ --- -
p, e -
\'
TABLE 3.2-1 Page 1 of 39 i BCGS CLASSIFICATION OF STRUC113RES, SYSTEMS, AND COMPONENTS Principal Quality Construc-Source Group tion on FSAR of Loca- Classi- Codes and Seismic Require-Section Supply tion cs:
fication Standa.de Category ments comments f tan ts: cs sea srs l PrincipalComponents{87 i
I
- I. Deactor systam 4.i 3 a. Reactor vessel and head GE A A III-At'3 I Y (*8 1
^
- b. Reactor vessel support skirt GE A NA III-A('8 ('8 l
- c. I Y l Reactor vessel appurtenances, GE A A III-A('8 I Y l pressure retaining portions
- d. CRO housing supports GE A NA III-NP
- e. Reactor internal structures, I Y GE A NA None I Y t:a3 engineered safety features
- f. Reactor internal structures, f
] GE A NA None other , NA N ( s sa {fg}N 4
- g. Control rode GE A NA None I Y
- h. Control rod drives GE A NA III-A('3 I Y
- i. Core support structure GE A NA None l
j 1 Power range detector hardware I Y GE A B III-2 I Y tass j k. Fuel assemblies GE A NA None
- 1. Reactor vessel stabiliser GE A NA I Y III-NF . I Y j II. thaclear Boiler System 5.1 j a. vessels, level instrumentation GE A A condensing chambers III-1 I Y
- b. vessels, air accumulators P A,C C
- c. Air supply check valves and III-3 I Y P A,C C III-3 I Y piping downstream of air
- supply check valves
- d. Piping, safety relief P A j C III-3 I Y valve discharge j e. Piping, main steam, within GE/P A,C A "'
III-1 Y outboard isolation valves I
! f. Piping, feedwater, within P A,C A III-1 Y j outboard isolation valves I
- q. Piping, siain steam, between P c B III-2 taas outhoard and outermost I Y isolation valves i h. Piping, feedwater, between P C B III-2 I Y t
- aa outboard and outermost isolation valves i
__N
~ ~ - - - _ . _ . . _ _ . . _. , ,
BCG2 FSAR C/Ow l YABLE 3.2-1 (cont) Page 5 of 39 l Principal Quality Construc-source Group tion QA FSAR of Loca- Classi- Codes and Seismi Dequire-section supply tion fication standards Category ments comments cas ta cas ses ces ces Principal components isolation valves GE C B PSV-IIt'l I Y
- 3. Pumps t*e3
- 4. Pues motors GE C NA NENA NG-It'3 I Y Y (*os ;
- 5. Valves, inboard isolation GE A A III-1 I C A III-1 I Y t**3
- 6. Valves, outboard isolation P
- and within .
Y caos
- 7. valves, beyond outermost P C B III-2 I
- containment isolation valves IEEE-279/323 I Y l S. Electrical modules with GE A,C NA j safety function tar 3 tses
- 9. Cable with safety function P A NA IEEE-279/323 NA Y C III-2 I Y
- l. 10. ECC8 jockey pump P B
- 11. ECCs jockey pump motors P c NA IEEE-323/344 I Y l
- c. High pressure coolant injection 6.3 ,
(BPCI) system:
P A,C A III-1 I Y taes I
- 1. Piping, within outermost i containment isolation valves Piping, test return line to P .C B III-2 I Y j 2.
condensate storage tank up f i to second isolation valve Pumps (main and booster) GE C B PSV-IIt*3 I Y
- 3. ta ST
- 4. EPCI turbine GE C NA VIII-1 I Y l
condensate pump J
Vacuum pump S condensate pu.np G:: C NA Mone NA N j* 7.
motore
' Piping, valve leakof f and P C B III-I I Y 8.
l cooling lines to barometric
> condenser Y <sestoss
! 9. Piping, other P C B III-2 I A,C A III-1 I Y ts'8E*es i 10. Valves, containment isolation P
- and within t aest ses Valves, other P C B III-2 I Y i . 11.
- 12. Electrical modules with GE C MA IEEE-279/323 I Y l
j safety function car 3
- 13. Electrical auxiliary equipment GE C NA Mone I Y i
Amendment 5 l i
e
7'---
. . -- ~
a
- (
ncGS PSAR e/se l t-TABLE 3.2-1 (cont) Page 7 of 39 l Principal Quality Construc-
.. Source e-Group tion DA FSAR of Loca- Classi- Codes and Seismic Require-Section Supply tion fication Standards Category ments Comments (s) t a) es) tes can cis Principal Components j C. Primary containment leakage 6.2.6 rate testing system:
i
- 1. Piping and valves, P c B III-2 I Y (**3 l containment penetration S isolation i
- f. MSIV sealing system: 6.7
- 1. Valves, outermost isolation P C A III-1
- 2. I Y t***
Valves, other, and piping P C B III-2 (*e3 I Y i 3. Electrical modules with saf4ty P C NA IEEE-279/323' I Y functior,a a 7 > l l
- VI. Beactor core isolation coo 1}pg 5.4.6 1 IFCICI system:
i
- 1. Piping, within outermost P A,C A III-1 I Y 8888 i
containment isolation valves
] 2. Piping, beyond outermost P C B III-2 I Y tses containment isolation valves a 3. Piping, test return to P C B III-2 I Y condensate storage tank up j to second isolation valve
} 4. Piping, valve leakoff 6 cooling P C B. III-2 I Y lines to barometric condenser
] 5. RCIC pump GE C B PSV-IIt*3 I Y
- 6. RCIC barometric condenser GE C NA VIII-It*3 NA N j 7. RCIC condensate pump and GE C MA None NA vacuum pump N
- 8. Condensate and vacuum pump GE C NA Mone NA
$ motors N j 9. Valves, containment isolation P A A III-1 I Y t:en ee J
and within i 10. Valves, other P C B
- 11. RCIC turbine III-2 I Y t to at ee
{ GE C MA VIII-1 tass 1 12. Electrical modules with GE C NA I Y l j safety function tart IEEE-279/323 I Y 2
- 13. Cable with safety function P C NA IEEE-279/323 NA Y tass i
- Amendesnt S l l
... . .r._ ..._ .._. . . . . . . -- - . .
ScoS rSha 4/s4 i TABLE 3.2-1 (cont) Page 32 of 39 l Principal Quality Construc-Source Group tion QA FSAR of Loca- Classi- Codes and Seis::ii; Dequire-Section supply tion fication Standards Category mente Comments (a) (ab (a) (s) (e3 (F3 Principal components I
- h. Reactor building / including P C NA AISC/ACI-318 I Y l
- pressure-retaining doors i
- i. Plant cancelled area P All NA AISC/ACI-318 I Y l in es /$4- s ak arrybne, revef e 1
xIx. .tr.ot ss)he 3.8 (...
i a. Station service water intake P 0,W NA AISC/ACI-318 I Y l i
structure
- b. Deleted l
- c. Diesel generator fuel tank room P G NA Mone I Y j d. Station battery rooms P B NA Mone I Y 1
- e. Spent fuel 5001, reactor well, 9.1.1, P C NA None I Y
- new fuel vault, dryer 9.1.2 separator pool, and cask pit
- f. Deleted l
. 4 Unit vent stack, North & South P O NA ACI-307 I SY l l h. Condensate storage tank dike P O NA ACI-318 I Y l 1
- 1. Spent fuel pool lir.er 9.1.2 P C NA Mone NA N --(k
(**8 i 1 Skinest surge tanks 9.1.1 P C NA None NA N
- k. Missile / jet barriers P A,B,C,G, NA AISC/ACI-318 I Y l j R,W i 1. Structural tackfill P O NA Mone I Y j m. Post accident shielding P A,B,C,G, NA ACI-318 I Y R,T
- n. Seismic Category I electrical P O NA ACI-318 I Y duct bank manholes i
l 1
i J
j Amendas nt S l
.- . . - - .. ~
.. . . g i
1 TABLE 3.2-1 (cont) Page 3g of 39 l
(* 78 Doct work is of non-Seismic category I design, but is installed and supported as Seismic category I.
f l
j (**3 Valve operators on safety related valves that must function are Q-listed and Seismic Category I
(*** Equipment is classified in accordance with the conformance statements made in Sections 7.2, 7.3, 7.4, 7.5 and 7.6 in reference to IEEE 279 paragr&jh 4.4 and IEEE-323.
cos) The QA Program controle applicable to equipment classified as Seismic II/I are in accordance
- with Regulatory Guide 1.29 commitments contained in FSAR Section 1.8 l toaa No QA Program controls applied during Design and Construction Phase. QA Programs controls
- during operation are applied to an extent consistent with the items importance to safety.
l taas OA Program controle for the fire protection program, inc~uding emergency lighting and communications, l are applied to the extent of the ten quality assurance criteria of Appendix A to Branch Technical j Position 9.5-1 and to an extent consistent with the item 8s/ activity's importance to safety.
l cos The recirculation system piping was built to both ASME Section III and B31.7 codes as required l
- by the GE design specification. The ASME Section III NPP-1 report requires signatures by a l j qualified inspector and also indicates that the pipe was built to the requirements of B31.7. t
, (*** Except north radwaste area of auxiliary building, since there are no Seismic Category I l J components in this area. I a
i Tla faadet presswet Je.ss) lkje.gw0 skudwunr. tolde.$. ar.1 acc& tira e'nclujoe) N (SS)kkI pyrw , wUek h cour d y 4 opr4aad aA ptgra .
l (S) Ang HoMicJih n tp ulad 4. E lb wdila edu.fd e +/e opetdied on pre- r .
l^ GDC s- Ja e (g 7),c.Co.nta.inIed cy. e.
arlS p.n t.b % ~ s-vb" Ybf""- ffcf 4. a p<(.+.ct,J
- .- e <.o.,,c,.,f-g
-e o .e ,o, eaf f6co se e du l
- (e s) n. w k i.ns t. <..e ence aa y~v 4 a Sunn ~m a c.w ..sn a ye,.s w Qn er.yw.
& ,.9y,,, usives & HPct a d Rctc % k e.s e e. py f _ M & sp A:o t o' (SQ ere x- . ,
1 Amendment S l
HCGS FSAR 6/84 for HCGS, an appropriate safety classification will be determined.
c.1 The HCGS position on TMI Item I.D.2 is given in Section 1.10. The safe.ty foram& disp /*y system /s par + f W t;,,.b.,/ Room
.n grMal A' g SpM Item XV.d of revised Table 3.2-1).
c.2 The HCGS position on TMI Item II.B.1 is given in Section 1.10. The HPCI, RCIC, ADS, and containment instrument gas systems are Q-listed, as shown in Items V.c, VI, XV.b.1, and XVII.b of Table 3.2-1. The RPV head vent is 0-listed but not Class IE (Item I.c of Table 3.2-1).
I c.3 The HCGS position on TMI Item II.B.2 is given in Section 1.10. The post-accident shielding is O-listed (Item XIX.m of revised Table 3.2-1).
c.4 The HCGS position on THI Item II.B.3 is given in Section 1.10. The post accident sampling system (PASS) is not Q-listed with the exception of the primary containment isolation and reactor coolant pressure boundary piping and valves.
c.5 The HCGS position on TMI Item II.D.3 is given in Section 1.10. The SRV position indication system is Q-listed (Item XV.d of revised Table 3.2-1).
c.6 The HCGS position on THI Item II.E.4.1 is given in Section 1.10. The dedicated hydrogen control penetrations are Q-listed (Item V.d.4.g and h of Table 3.2-1).
l c.7 The HCGS position on TMI Item II.E.4.2 is given in Section 1.10. Containment isolation valves are Q-listed (See Table 3.2-1 under applicable system).
c.8 The HCGS position on TMI Item II.F.1 is given in Section 1.10. Accident monitoring instrumentation will be designed ;
in accordance with the guidance provided in Regulatory i Guide 1.97, Rev 2. This instrumentation will be reviewed for classification as Q-listed, and Table 3.2-1 will be l modified as necessary.
> c.9 The HCGS position on TMI Item II.F.2 is given in Section 1.10. No additional instrumentation was identified as a result of this required study, and therefore no changes to l
! Table 3.2-1 are necessary at this time.
l1 c.10 The HCGS position on TMI Item II.K.3.13 is given in Section 1.10. No change was made to the HPCI and RCIC initiation
!l levels and,.therefore no change to Table 3.2-1 are Li
- necessary.
SRAI (1)-10 Amendment 6 l
l
, c.11 The HCGS position on TMI Item II.k.3.15 is given in Section i
1.10. The HPCI and RCIC leak detection systems are.-O-listed (Item XV.e.2 of Table 3.2-1). ,
c.12 The HCGS position on TMI Item II.k.3.16 is given in Section 1.10. HCGS is reviewing the modifications proposed by the BWROG to meet the requirements. This review will be completed by December, 1983. Table 3.2-1 will be modified as appropriate.
c.13 The HCGS position on TMI Item II.k.3.18 is given in Section 1.10. BWROG response to this TMI study is still under evaluation by NRC. HCGS design will.be modified to comply l with the NRC's acceptable position. Table 3.2-1 will be modified as appropriate.
c.14 The HCGS position on TMI Item II.k.3.21 is given in Section 1.10. No change was made to the core spray and LPCI logic and therefore no. change to Table 3.2-1 is necessary. ,
c.15 The HCGS position on TMI Item II.k.3.22 is given in Section 1.10. The RCIC suction transfer is Q-listed (Item XV.c.1 of Table 3.2-1).
- c.16 The HCGS position on TMI Item II.k.3.24 is given in Section 1.10. The HPCI and RCIC room unit coolers are Q-listed (Item XIII.c.2 of revised Table 3.2-1).
c.17 The HCGS position on TMI Item II.k.3.25 is given in Section 1.10. The recirculation pump sealing cooling water supply system (RAC and CRD) are not Q-listed (Item XI.c and IV of L Table 3.2-1),
i c.18 The HCGS position on TMI Item II.k.3.27 is given in Section 1.10. See Table 3.2 for listing of existing level instrumentation.
c.19 The HCGS position on TMI Item II.k.3.28 is given in Section 1.10. The ADS valves, accumulators and associated equipment and instrumentation are 0-listed (Item II.1, II b, II.c XV.b.1 & 11 and XVII.b of Table 3.2-1).
c.20 The HCGS position on TMI Items III.a.1.1/III.a.2 is given in Section 1.10. Activities covered by the QA program are delineated in Table 17.2-1 and include emergency plans under, " combating emergencies and other significant events."
c.21 The HCGS position on TMI Item III.a.1.2 is given in Section 1.10. The Emergency Asy.ase, . %cilities M Acperdh,, 57 ERFDA is s4.En s'n (Itiem XV.d off Table 3.2-1).
Urtv/"l '-
SRAI (1)-11 Amendment 6 N[
,,l.L. l YS
'13l; A; '
i
HCGS FSAR 6/84 of revised Table 3.2-1). However, it is designed to accommodate design flood and seismic event.
nnd meMenks 6 +ks- root
- destn*y. sp% a^n-e) The roof drainage system 483L not Q-listed and AR{ Tot a
" structure system or component" that should be included in Table 3.2-1. Roof drainage cannot adversely impact safety-related equipment because of flood protection measures Tppl.J;fh,$8h*r.. f* Erst- Sa i i n G-laT'l 85 f rt e f tAs. Q stiwb.
Site grading should not be included in Table 3.2-1 as discussed in the response to item a.20 of SRAI(1).
f) The purge (containment inerting) system is described under the containment atmosphere control system (Item V.d.3), not the reactor building ventilation system (Item VIII.c).
g) Containment isolation valves used at HCGS meet the requirements outlined in GDCs 54-56 of 10 CFR 50 Appendix A l as outlined in Table 6.2-16.
h) Table 3.2-1, Item V.a has been revised to clearly identify piping, valves and other equipment used for suppression pool cooling, steam condensing and suction lines for the shutdown
' cooling modes of the RHR system.
i) There are no nuclear codes and standards applicable to the design and manufacture of the HPCI and RCIC turbines.
l Approximately 50 to 75 components of the turbines' lubricating oil systems contribute to the electrohydraulic .
control of the governing valves. Footnotes (11) 555 (48)and(fh provide the applicable quality assurance, documentation, maintenance, and material fabrication information.
j) Process and effluent radiation monitoring systems are listed in Item X.d of Table 3.2-1. See Sections 7.6 and 11.5 for i* the differences between the process radiation monitoring
! systems and the process and effluent radiation monitoring systems.
k) Table 3.2 1 will be revised to incorporate the Emergency Response Facilities Data Acquisition System (ERFDAS).
- l. This system is non-Q, non-class IE and non-seismic,except for the Class IE isolation devices supplied with the ERFDAS.
- 1) The MSIV sealing system consists of valves, valve operators, and piping only; the sealing system is supplied by the instrument gas system (see Item XVIII.b).
m) The unit vent stacks are 0-listed as shown in revised
- l. Table 3.2-1, Item XIX.g.
I SRAI (1)-13 Amendment 6 i
ll
4 BCGS PSAR 4/84 l YABLE 3.2-1 (cont) Page 24 of 39 l 4
l
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- source Group tion OA FSAR of Inca- Classi- Codes and Seismic Require-
. Section supply tion fication standarde Category monte Comments
- <ss cas ,c s ces (as cra Principal C e ts
) '
- 6. Containment atmosphere P A,B,C NA IEEE-279 I Y l control system
. 7. Main steam isolation valve P C NA IEEE-279 I Y sealing system l
S. Piltration, recirculation, P B,C NA IEEE-279 I Y
- and ventilation system l 9. Reactor building ventilation P c NA IEEE-279 I Y I isolation system *
- 10. Main control room habitability P B NA IEEE-279 I Y and isolation system
- 11. Essential auxiliary supporting P All NA IEEE-279 I Y
, systems for engineered safety i
features control
.)'
- c. Controle and instrumentation 7. 4
- associated with safe shutdown systems
- 2. Standby liquid control (sir) GE C NA IEEE-279 I Y t' systee
- 4. Remote shutdown systems P R NA IEEE-279 I Y l
- 5. Essential auxiliary supporting GE/P All NA IEEE-279 I Y l systems for the safe shutdown j systems 1
l d. Safety-related display - . .T - __
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ATTACHMENT II FSAR CHANGES RESULTING FROM LICENSEE QUALIFICATIONS BRANCH MEETING - JULY 23, 24&25, 1984 t
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HCGS FSAR 1.10 TMI-2 RELATED REQUIREMENTS FOR NEW OPERATING LICENSES e
1.10.1 NUREG-0737, CLARIFICATION OF THE TMI ACTION PLAN REQUIREMENTS Following the accident at Three Mile Island (TMI) Unit 2, the i
Nuclear Regulatory Commission (NRC) developed the TMI Action Plan, NUREG-0660, to provide a comprehensive and integrated plan for improving the safety of power reactors. NUREG-0737 was issued with an October 31, 1980 letter from D.G. Eisenhut, NRC, to licensees of operating power reactors and applicants for operating licenses forwarding specific TMI-related requirements from NUREG-0660 which have been approved by the NRC for
).. implementation at this time. In this NRC report, these specific requirements comprise a single document which includes additional information about implementation schedules, applicability, method of implementation review by the NRC, submittal dates, and clarification of technical positions. The total set of TMI-related actions have been documented in NUREG-0660, but only those items that the NRC has approved for implementation to date are included in NUREG-0737.
Enclosure 2 to NUREG-0737 lists TMI Action Plan requirements for i
operating license applicants. FSAR Section 1.10.2 itemizes these requirements sequentially according to the NUREG-0737 nuniber.
o Each item is accompanied by a response and/or reference to a l section in the FSAR that further discusses how Public Service Electric and Gas Company (PSE&G) or the Hope Creek Generating Station (HCGS) design complies with the requirement. These l
responses will be revised periodically as ongoing efforts to address each requirement are completed.
! 1.10.2 TMI ACTION PLAN REQUIREMENTS FOR APPLICANTS FOR AN OPERATING LICENSE (ENCLOSURE 2 TO NUREG-0737)
- I.A.1.1' SHIFT TECHNICAL ADVISOR Position Each applicant shall provide an on-shift technical advisor to the shift supervisor. The shift technical advisor (STA) may serve l
more than one unit at a multiunit site if qualified to perform l the advisor function for the various units.
1.10-1 i
l
a 7
HCGS FSAR The STA shall have a bachelor's degree or equivalent in a scientific or engineering discipline and have received specific
, training in the response and 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 and the contro1* room. The applicant shall assign
- normal duties to the STAS that pertain to the engineering aspects of assuring safe operations of the plant, including the review .
and evaluation of operating experience.
Clarification (1) Due to the similarity in the requirements for dedication to safety, training, and onsite location and the desire that the accident assessment function be performed by someone whose normal duties involve review of operating experiences, our preferred position is that the same people
' perform.the accident and operating experience assessment function. The performance of these~two functions may be split if it can be demonstrated the persons assigned the
' accident assessment role are aware, on a current basis, of the work being done by those reviewing operating l
experience,
'(2) To provide assurance that the STA will be dedicated to concern for the safety of the plant, our position has been i
the STAS must have a clear measure of independence from i
duties associated with the commercial operation of the plant. This would minimize possible distractions from safety judgments by the demands of commercial operations.
l l
We-have determined that, while desirable, independence from the operations staff of the plant is not necessary to i' pecvide this assurance. It is necessary, however, to clearly emphasize the dedication to safety associated with
' the STA position both in the STA job description and in the It is not acceptable to personnel filling this position.
assign a person who is normally the immediate supervisor of the shift supervisor to STA duties as defined herein.
i It is our position that the STA should be available within (3) i 10 minutes of being summoned and therefore should be l
onsite. The onsite STA may be in a duty status for periods of time longer than one shift, and therefore asleepIt at is some l times, if the 10-minute availability is assured.
(
l preferable to locate those doing the The desired operating exposure experience to the operating assessment onsite. l l
l plant and contact with the STA (if these functions are to 1.10-2 i
1
HCGS FSAR 8/84 be split) may be able to be accomplished by a group, normally stationed offsite, with frequent onsite presence.
We do not intend, at this time, to specify or advocate a minimum time onsite.
Response
The STA function will be provided, on shift, by an individual meeting the experience, education, and training requirements as a specified in NUREG-0737 and ANS 3.1-1981. The proposed supervisory shift crew composition for conditions 1 through 3 consists of one senior nuclear shif t supervisor (SNSS-SRO), one nuclear shift supervisor (NSS-SRO), and two nuclear control operators (NCO-RO). In the event that neither the SNSS nor the NSS are STA qualified, an additional person who is STA qualified will be assigned.
Various proposals for meeting the STA on shift requirement are currently under review by the Institute for Nuclear Power Operations (INPO) and the NRC. The final recommendations of these studies will be incorporated into station procedures.
The STA will have a bachelors degree or equivalent in a scientific engineering discipline with specific training in plant design and response and analysis of the plant for transients and accidents in accordance with the requirements of NUREG-0737,Section I.A.l.l.
During normal operations, the STA may be assigned responsibilities that pertain to the engineering aspects of ensuring safe operations of the plant.
See Section 13.1 for further discussion.
Training procedure TP-303, Shif t Technical Advisor Training and Certification, meets the requirements of NUREG-0737, ANSI 3.1-1981, and 10CFR55. The Hope Creek specific TP-303 will be in place by March, 1985. The content of this program is described in FSAR Section 13.2.1.
1.10-3 Amendment L
t HCGS FSAR 8/84 I.A.l.2 SHIFT SUPERVISOR RESPONSIBILITIES Position ,
Review the administrative duties of the shif t supervisor and delegate functions that. detract f rom or are subordinate to the management responsibility for assuring safe operation of the plant to other personnel not on duty in the control room.
Clarification (1) The highest level of corporate management of each licensee shall issue and periodically reissue a management directive that emphasizes the primary management responsibility of the shift supervisor for safe operation of the plant under all conditions on his shift and that clearly establishes his command duties.
(2) Plant procedures shall be reviewed to assure that the duties. responsibilities, and authority of the shift supervisor and control room operators are properly defined to effect the establishment of a definite line of command and clear delineation of the command decision authority of the shif t supervisor in the control room relative to other plant management personnel. Particular emphasis shall be placed on the following:
(a) The responsibility and authority of the shift supervisor shall be to maintain the broadest perspective of operational conditions af fecting the safety of the plant as a matter of highest priority at all times when on duty in the control room. The principle shall be reinforced that the shift supervisor should not become totally involved in any single operation in times of emergency when multiple operations are required in the control room.
(b) The shif t supervisor, until properly relieved, shall remain in the control room at all times during accident situations to direct the activities of control room operators. Persons authorized to relieve the shift supervisor shall be specified.
1.10-4 Amendment
F HCGS FSAR 8/84 (c) If the shift supervisor is temporarily absent from the control room during routine operations, a lead control room operator shall be designated to assume the control room command function. These temporary duties.
responsibifities, and authority shall be clearly specified.
(3) Training programs for shift supervisors shall emphasize and reinforce the responsibility for safe operation and the management function that the shift supervisor is to provide for assuring safety.
(4) The administrative duties of the shift supervisor shall be reviewed by the senior officer of each utility responsible for plant operations. Administrative functions that detract from or are subordinate to the management responsibility for assuring the safe operation of the plant shall be delegated to other operations personnel not on duty in the control room.
Re sponse A written policy describing the primary management responsibilities of SS-SROs and establishing their command duties was placed in ef fect September 12, 1979, and reissued by the vice president - nuclear as VPN-PLP-01.
The guidance of this policy, along with duties, responsibilities, and authority of the SS-SRO is promulgated in Administrative Procedu re S A- AP.22-002( O) , Station Organization and Responsibilities.
The shift command function responsibilities are promulgated in Operations Department Administrative Procedure OP-AP. ZZ-002(O) ,
Conduct of Operations.
Shif t administrative duties which detract f rom the SS-SRos responsibility for safe operation of the plant will be assigned to the shif t clerks and/or the ' Operations Staf f Group as appropriate.
l 1.10-5 Amendment
I HCGS FSAR See Section 13.1.2 for further discussion.
e I.A.1.3 SHIFT MANNING 1
Position .
Assure that the necessary number and availability of personnel to man the operations shifts have been designated by the licensee.
Administrative procedures should be written to govern the movement of key individuals about the plant to assure that qualified individuals are readily available in the event of an abnormal or emergenc? situation. This should consider the recommendations on overtime in NUREG-0578. Provisions should be made for an aide to the shift supervisor to assure that, over the long term, the shift supervisor is free of routine administrative duties.
C1arification At any time a licensed nuclear unit is being operated in Modes 1-4 for a pressurized water reactor (power operation, i startup, hot standby, or hot shutdown, respectively) or in Modes 1-3 for a boiling water reactor (power operation, startup, or hot shutdown, respectively), the minimum shift crew shall include two licensed senior reactor operators, one of whom shall i be designated as the shift supervisor, two licensed reactor l operators, and two unlicensed auxiliary operators. For a multi-unit station, depending upon the station configuration, shift staffing may be adjusted to allow credit for licensed senior reactor operators and licensed reactor operators to serve as relief operators on more than one unit; however, these individuals must be properly licensed on each such unit. At all other times, for a unit loaded with fuel, the minimum shift crew shall include one shift supervisor who shall be a licensed senior reactor operator, one licensed reactor operator, and one i
unlicensed auxiliary operator.
, Adjunct requirements to the shift staffing criteria stated above L
, are as follows:
l (1) A shift supervisor with a senior reactor operator's j license, who is also a member of the station supervisory staff, shall be onsite at all times when at least one unit is loaded with fuel.
1.10-6
1
- HCGS FSAR (2) A licensed senior reactor operator shall, at all times, be in the control room from which a reactor is being operated.
The shift supervisor may from time to time act as relief operator for the licensed senior reactor operator assigned
' to the control room. o (3) For any station with more than one reactor containing fuel, the number of licensed senior reactor operators onsite shall, at all times, be at least one more than the number of control rooms from which the reactors are being operated.
(4) In addition to the licensed senior reactor operators specified in (1), (2), and (3) above, for each reactor containing fuel, a licensed reactor operator shall be in the control room at all times.
(5) In addition to the operators specified in (1), (2), (3),
and (4) above, for each control room from which a reactor is being operated, an additional licensed reactor operator shall be onsite at all times and available to serve as
' relief operator for that control room. As noted above, this individual may serve as relief operator for each unit being operated from that control room, provided he holds a
- current license for each unit.
(6) Auxiliary (non-licensed) operators shall be properly qualified to support the unit to which assigned.
(7) In addition to the staffing requirements stated above, shift crew assignments during periods of core alterations shall include a licensed senior reactor operator to I
directly supervise the core alterations. This licensed senior reactor operator.may have fuel handling duties but shall not have other concurrent operational duties.
i Licensees of operating plants and applicants for operating licenses shall include in their administrative procedures (required by license conditions) provisions governing required l
shift staffing and movement of key individuals about the plant.
These provisions are required to assure that qualified plant i
personnel to man the operational shifts are readily available in l
the event of an abnormal or emergency situation.
l I
1.10-7 l
L
- HCGS FSAR These administrative p..eedures shall also set forth a policy, the objective.of whica is to operate the plant with the required staff and develop working schedules such that use of overtime is avoided, to the extent practicable, for the plant staff who
- perform safety-related functions (e.g., senior reactor operators,
- health physicists, auxiliary operators, instrumentation an,d control technicians, and key maintenance personnel).
i l
IE Circular No. 80-02, " Nuclear Power Plant Staff Work Hours,"
dated February 1, 1980, discusses the concern of overtime work for members of the plant staff who perform safety-related functions.
We recognize that there are diverse opinions on the amount of overtime that would be considered permissible and that there is a lack of hard data on the effects of overtime beyond the generally
- recognized normal 8-hour working day, the effects of shift rotation, and other factors. We have initiated studies in this area. Until a firmer basis is developed on working hours, the administrative procedures shall include as an interim measure the following guidance, which generally follows that of IE Circular
! No. 80-02.
In the event that overtime must be used (excluding extended periods of shutdown for refueling, major maintenance, or major plant modifications), the following overtime restrictions stould be followed.
(1) An individual should not be permitted to work more than 12
- hours straight (not including shift turnover time).
(2) There should be a break of at least 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> (which can i include shift turnover time) between all work periods.
l I
(3) An individual should not work more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in any 7-day period.
(4) An individual should not be required to work more than 14 consecutive days without having 2 consecutive days off.
I However, recognizing that circumstances may arise requiring deviation from the above restrictions, such deviation shall be authorized by the plant manager or his deputy or higher levels of 1.10-8
HCGS FSAR 8/84 management'in accordance with published procedures and with appropriate documentation of the cause. If a reactor operator (RO) or senior reactor operator (SRO) has been working more than 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> during periods of extended shutdown (e.g., at duties away from the control board), such individuals shall not b'e ,
assigned shift daty in the control room without at least a 12-hour break preceding such an assignment. We encourage the development of a staffing policy that would permit the licensed reactor operators and senior reactor operators to be periodically relieved of primary duties at the control board, such that periods of duty at the board do not exceed about 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> at a time. If a reactor operator is required to work in excess of 8 continuous hours, he shall be periodically relieved of primary duties at the control board, such that periods of duty at the board do not exceed about 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> at a time.
The guidelines on overtime do not apply to the STA provided that the STA is provided sleeping accommodations and 10-minute availability is assured.
Operating license aplicants shall complete these administrative procedures before fuel loading. Development and implementation of the administrative procedures at operating plants will be reviewed by the Office of Inspection and Enforcement beginning 90 days af ter July 31, 1980.
Re sponse See Section 13.1.2 for discussion on shif t manning and operating shift crews.
Operations Department Procedure OP-AP.22-002(O) , Conduct of Operations, establishes maximum work hours for licensed operators and implements current NRC policy including policy statement on nuclear power plant staff working hours dated 2/11/82 and Generic Le tter 8 2-12.
Adequate shift coverage shall be maintained without routine excessive use of overtime. The objective shall be to have operating personnel work a normal 8-hour day while the plant is operating to meet the rotating schedule requirements of the department. Howeve r , in the event that unforeseen problems require substantial amcunts of overtime to be used: or during 1.10-9 Amendment
t HCGS FSAR 8/84 exter.ded periods of shutdown for refueling, major maintenance, or major plant modifications, on a temporary basist the following guidelines shall be followed:
- a. An individual should not be permitted to work more than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> strhight, excluding shift turnover time.
- b. An individual should not be permitted to work more than !
16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> in any 24-hour period, nor more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in any 48-hour period, nor more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in any 7-day period, all excluding shift turnover time,
- c. A break of at least 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> should be allowed between work pe,riods, including shift turnover time.
- d. Excep/duringextendedshutdownperiods,theuseof over$e should be considered on an individual basis and not for the entire staff on a shift. ,
Any deviation from the above guidelines shall be authorized by f the operations manager or higher levels of management, with '
documentation of the basis for granting the deviation.
Overtime shall be reviewed monthly by the general manager or his ,
designee. j L
Shift manning is described in Section 13.1.2 and procedure :
OP- AP.22-002(Q) , Conduct of Operations.
I.A.2.1 IMMEDIATE UPGRADING OF OPERATOR AND SENIOR f OPERATOR TRAINING AND OUALIFICATION I Position 7 Applicants for SRO license shall have 4 years of responsible !
power plant experience, of which at least 2 years shall be nuclear power plant experience (including 6 months at specific i plant) and no more than 2 years shall be academic or related :
technical training. After fuel loading, applicants shall have 1 year of experience as a licensed operator or equivalent. t 1.10-10 Amendment
sm
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.s 4 4- See 'Section f3 l' for discussion of the PSE&G and HCGS
,organi2laiions. { .
~
1 General Manager - nuclear safety review group reports directly to N..ithe Vice President - nuclear.as discussed in Section 13.4.4 and
- shown on Figure 13.1-8.e ~
k .O . I.C.1 SHORT-TERMiACCIDENT ANALYSIS AND PROCEDURE REVIEW a.
3 -
+ y m,1 s} e
"'.. Poriition:N- ,c r , -~, ,, .. s
+ .Id our letters of S$ptember 13 and 27, October 10 and 30, and ~
6 .- ]Iovember L 9, 1979, ws required licensoes of operating plants,
- m. applicants fcr operating licenses, and licensees of plants under construction'to perform analysos'of transients and accident, J prkp'afe eme'sgency procedure g^uidelines, upgrade emergency
. - > procedures,'and to: conduct 3 operator retraining,(see also Item 7' ,I . AO2.1 o f this' repost) . Emergency procedures!are required to be jconsistent with the actions necessary to cop'e with the transients
,s 'and Eccidents analyzed. Analyses of transients and accidents
~2 ;wereyto be c6mplet'ad in early_1980, andfimplementation of
'tr procedures and retraining were to be completed 3 months after x : emergency ' proc'edure guidelines were esEablished ; .however, some VdifficultyVin completing these requirements has been experienced.
Clarification Lof-the scope of the task and appropriate schedule 8 revisions were included in NUREG-0737, Item I.C.I.
['
' ;a: y _ 7l .
Pending % staff appr. oval of the : revised analysis and guidelines, a f., # t' he 'staif will;icontinue the pilot monitoring of emergency h proco'dUresL desccibed Jn Item I.C.8 ( NUREG-0660) .. The adequacy of
- ' $ xthe boiling; water reactor vendor's quidelin6s will be identified '
4 to.'each neaE-term operating licensie during the emergency
,o procedure.rev ew. i ' '
m .. 9 __ g_ ,. ,
"3
- .3,;ew Response _
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<All' emergan,cy_ procedures 'will (be, writiten following the guidelines g, of the ~ BW'A Owners Group-Emergent;y Proceduras Committee, as long 5.yx ;a's. the guidelirids do .not contradict existing NRC directives, np These , procedures will bravailsble Marchf 1, 1985.
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-- 1.10'17 Amendment
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s HCGS FSAR 8/84 Corrections will be made, as necessary based on nny NRC audits
-of these procedures.
The Emergency Operating Procedures for HCGS will comply with NUREG-0737, ' Supplement 1, Section 7.0. I.C.2 SHIFT RELIEF AND TURNOVER PROCEDURES Position The licensee shall review and revise as necessary the plant procedure for shfft and relief turnover to assure the following: (1) A checklist shall be provided for the oncoming and offgoing control room operators and the oncoming shift supervisor to complete and sign. The following items, as a minimum, shall be included in the checklist: (a) Assurance that critical plant parameters are within allowable limits (parameters and allowable limits shall be' listed on the checklist). (b) Assurance of ?.he availability and proper alignment of all systems essential to the prevention and mitigation of operational transients and accidents by a check of the control console. What to check and criteria for acceptable status shall be included on the checklist. (c) Identification of systems and components that are in a degraded mode of operation permitted by the Technical Specifications. For such systems and components, the length of time in the degraded mode shall be compared with the Technical Specifications action statement. (This shall be recorded as a separate entry on the
- checklist.)
L (2) Checklists or logs shall be provided for completion by the of fgoing and oncoming auxiliary operators and technicians. Such checklists or logs shall include any equipment under maintenance or test that by itself could degrade a system critical to the prevention and mitigation of operational transients and accidents or initig e an operational transient .(what to check and critYeria for acceptable status shall be included on the checklist: and 1.10-18 Amendment
4 4 HCGS FSAR 8/84 (3) A system shall be established to evaluate the effectiveness of the . shif t and relief turnover procedures ( for example, periodic independent verification of system alignments). Re sponse The required checklists and logs addressing shift turnover are j specified ' in Operations Department Procedure OP-AP. ZZ-107(Q) ,
- Shif t Relief and Turnover.
The effectiveness of, ang d compliance with the shift turnover procedure shall be auditJed n accordance with procedure OP- AP. Z Z-017( O) , Operations partment Management Audit Program. I.C.3 ~ SHIFT SUPERVISOR RESPONSIBILITIES
- This item is included with Item I. A.l.2, Shift Supervisor Duties.
Response
A' discussion of this item is provided in the response to Item I.A.l.2. I.C.4 CONTROL ROOM ACCESS Position The licensee shall make provisions for limiting access to the control room to those individuals responsible for the direct operation of the nuclear power plant (e.g., operations supervisor, shift supervisor, and control room operators), to technical advisors who may be requested or required to support i operation, and the predesignated NRC personnel. Provisions shall include the-following: (1) Develop and implement an administrative procedure that establishes the authority and responsibility of the person
- in charge of the control room to limit access.
t-l 1.10-19 Amendment l i
HCGS FSAR g/84 (2) Develop and implement procedures that establish a clear line of authority and responsibility in the control room in the event of an emergency. The line of succession for the person in charge of the control room shall be established and limited to persons possessing a current senior reactor operator's license. The plan shall clearly define the. lines of communication and authority for plant management personnel not in direct command of operations, including those who report to stations outside the control room.
Response
The lines of' responsibility and authority of the SNSS-SRO, or the individual assuming the control room command function (as promulgated in procedure VPN-PLP-01) permit limited access to the control room area. This authority is delineated in S A- AP. Z Z-0 0 2( O) , Station Organization and Operating Practices, and OP- AP. ZZ-002( O) , Conduct of Operations. This item is also Ldiscussed in the response to item I.A.l.2. Chapter 13 I.C.5 FEEDBACK OF OPERATING EXPERIENCE Position Each licensee will review its administrative procedures to assure that operating experience from within and outside the organization is continually provided to operators and other operational personnel and is incorporated in training programs.
Response
An integrated nuclear department procedure is being prepared, and will be available by March 1, 1985. When issued, station proceduros will be revised to incorporate the prescribed procedure. Operating department procedure OP-AP.ZZ-105(O) will be used to disseminate information to Operating department personnel. 1.10-20 Amendment
i e HCGS FSAR' . 8/84 Industry operating experiences including events occurring within the organization are' reviewed for applicability to Hope Creek by the Reliability and Assessment Department. Pertinent information is communicated to the appropriate department for their information and any actions required are tracked until they have been satisfactorily completed. In addition, information is communicated to the Manager - Nuclear Training for incorporating
-new material into the Training Programs. The activities of the - Reliability and Assessment Department with respect to operating - experiences (i.e., INPO's SEE-IN Program) are governed by procedure M3-POP-001 " Operating Experience Review Progra Vendos. technical documents describing the operation and maintenance of installed equipment and components associated with Hope Creek Generating Station shall be controlled in the following manner,
- 1) Whenvendordocumentsarereceivedbydishplineswithin
-the Nuclear Department, these documents will be
" forwarded to the Nuclear Engineering Department for review and approval for inclusion into the vendor Document Control System.
- 2) Once approved by the cognizant engineer they will be
. assigned a-unique number and distributed to all user departments, and incorporated in procedures *and training as necessary.
Information. on operating experience provided by the NRC through
. the I & E Bulletins /Information Notices, generic letters and letters on the' docket are processed by nuclear licensing and regulation department within the nuclear department. These letters are distributed to various disciplines within nuclear ~ department for feedback of information. - Response action form is
- utilized-when a response or action is required and is monitored
, through the response tracking system to completion. In addition, the Nuclear Department Training Center has revised the two procedures pertaining to this subject to include HCGS. The procedures are TP-306HC, Plant Design Review Program, and TP-307HC, Operational- Experience Review Program. These procedures will be revised as necessary to incorporate the
~ ' integrated nuclear department procedure.
1.10-20a Amendment
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HCGS FSAR 8/84 I.C.6 VERIFY CORRECT PERFORMANCE OF OPERATING ACTIVITIES Position
-It is required (from NUREG-0660) that licensees' procedures be
. reviewed and revised, as necessary, to assure that an effective
~ system of verifying the correct performance of operating activities is provided as a means of reducing human errors and
-improving the' quality of normal operations. This will reduce the frequency of occurrence of situations that could result in or contribute to accidents. Such a verification system may include automatic system status monitoring, human verification of operations, and maintenance activities independent of ,the people performing the activity (see NUREG-0585, Recommendation 5) , or both.
Response
Verification of operating activities to provide a means of
" . reducing human errors and to improve the quality of normal operations shall be assured by the following procedures:
.a) .OP-AP.22-108(O) Removal and Return of Equipment to Service shall be used to track equipment out of service, determine if the equipment is safety-related, determine if a Limiting Condition for Operation exists, determine
-if independent verification is required, and determine the pre and post testing requirements.
I b) OP- AP. Z Z-109 ( 0 ) Equipment Operational Contract shall y contain the requirements to prevent unauthorized operation of equipment by establishing panel and valve
- . lock and tagging control.
c) OP- AP. Z Z-00 2( 0) Conduct of Operations will be revised to
, include independent verification requirements for safety related system line-ups.
i d) SA-AP.ZZ-12(Q) Surveillance Program shall contain the requirements for' independent' verification of safety related system line-up and. temporary modification for testing.. In addition this procedure will require, prior to start of testing, permission f rom designated operations personnel holding an SRO license. i i I , 1.10-21 Amendment i l
! l 1
O HCGS FSAR 8/84 e) SA-AP.ZZ-15(O) Safety Tagging shall include reference to OP-AP.ZZ-108(O) and independent verification of, installation and removal of Temporary Grounding Tags used on safety-related equipment. f) SA-On.ZZ-009 Control of Station Maintenance shall includo requireraents to obtain prior permission to work on plant equipment from designated operations personnel holding an SRO license. g) SA-AP.ZZ-13(0) Jumper and Lif ted Leads shall include independent verification requirements for installation of temporary modification on safety related systems. The above procedures shall contain identification of activities requiring independent verification, responsible person to perform the verification, and the method of documenting the performance verification for safety-related equipment. In addition an Operating Department audit procedure OP-AP.ZZ-017(O) shall specify periodic audit requirements of operational activities included but not limited to the above procedures. I.C.7 NSSS VENDOR REVIEW OF PROCEDURES Position s Obtain nuclear system supply system vendor review of power-ascension and emergency operating procedures to further verify their adequacy.
Response
All startup test procedures from core load through power ascension will be reviewed by GE. This review, as well as vendor review of tests results, will be documented prior to commercial operation. 1.10-21a Amendment
HCGS FSAR 8/84 Chapter 13 , CONDUCT OF OPERATION 13.1 ORGANIZATION STRUCTURE Public Service Electric and Gas Company (PSE&G) is an investor-owned public utility providing reliable generation, transmission, and sale of gas and electric energy in the State of New Jersey. In meeting these responsibilities to our customers, we have developed experience and expertise in the design, construction, startup, and operation of both fossil and nuclear generation facilities. In continuing these commitments, PSE&G is dedicated to the safe, reliable, and efficient operation of Hope Creek Generating Station (HCGS). Figures 13.1-1 and 13.1-2 aro organization charts showing the corporate structure and the office of the senior vice president of nuclear and engineering, respectively. l 13.1.1 MANAGEMENT AND TECHNICAL SUPPORT ORGANIZ ATION The management and technical support organization is as follows:
- a. Senior vice president - nuclear and engineering - As l shown on Figure 13.1-2, the senior vice president -
nuclear and engineering is responsible for the direction and management of engineering and construction, nuclear, and nuclear assurance and regulation departments.
- b. Vice president - engineering and construction - The vice president - engineering and construction is responsible for the engineering, design and construction services required to build new facilities. Similar services are rendered to support major modifications to existing facilities.
Planning and executing this work to meet schedules, budgets, and technical requirements are major commitments. Figures 13.1-3 and 13.1-4 identify the engineering and construction department. 13.1-1 Amendment
HCGS FSAR , 8/84
- c. Vice president - nuclear - The vice president -
nuclear, as the senior nuclear manager, is , responsible for the overall direction and control of , the company's nuclear program. Besides having responsibility for the operations and maintenance of the nuclear facilities, he directs services, technical, and engineering support for the operating nuclear plants. Figure 13.1-6 identifies the nuclear department.
- d. General manager - nuclear assurance and regulation -
- The general manager - nuclear assurance and regulation is responsible for providing management with an independent assessment of the effectiveness of nuclear safety and quality programs, managing licensing and analysis efforts for facilities under construction, and managing environmental efforts to obtain approvals for existing and new facilities.
He provides an independent assessment of regulatory requirements and developments relevant to energy supply and engineering activities (Reference Figure 13.1-14). 13.1.1.1 Design and Operating Responsibilities For the Hope Creek project, the principal site engineering design of the plant, procurement of material and equipment, and construction of the plant are performed by Bechtel Power Corporation. A project team, under the vice president - engineering and construction, has been established to direct and managetheconstructioneffortsthroughp@poperationaltestingto fuel load. The vice president - nuclear provic es an experienced and trained core staff load, forpower Hope Creek to support ascension p@d the testing, an continued safe,yoperational testing, reliable, and ef ficient commercial operation of the nuclear f acility, fs 13.1.1.1.1 Design and Construction Activity (Project Plans) The.vice president - engineering and construction has the corporate responsibility and authority of the completion of HCGS. He has extended his authority to the project manager of 13.1-2 Amendment t
I HCGS FSAR 8/84 f Hope Creek and' established a project team to supoort this effort. The project organiza ion enables the Hope Creek project to use the resources and experience of PSE&G engineering and construction departments and divisions. This project organization is identified on Figure 13.1-5. All of the Bechtel Power Corporation functions are performed in cooperation with the PSE&G organization of like functions, under the management supervision of the Hope Creek project team, which has four major project objectives:
- a. To complete HCGS on schedule and within budget
- b. To ensure that all necessary organizations support the project in an effective and timely manner
- c. To ensure that quality assurance is being effectively addressed within the project
- d. To ensure that adequate safety and reliability criteria for engineering, design, and installation i are met.
The project team provides the detailed management for the project and consists of the project manager, chief project engineer, project construction manager, project licensing manager, startup manager, and assistant projecg manager. Each of these team members is responsible for c@dinating his organization's management and efforts witn other PSE&G departments. The responsibilities of the project team members are as follows:
- a. Project manager - The project manager has the management responsibility and necessary authority to complete the Hope Creek project. In doing so, he is l
accountable for overall project performance to the vice president of engineering and construction. The l project manager is the chief spokesman for the i project as the head of the project team until fuel I load. l b. Chief project engineer - The chief project engineer l is responsible for the coordination of Bechtel and PSE&G engineering. He is responsible for providing ! Bechtel with design criteria, licensing and l' l l - 13.1-3 Amendment
l HCGS FSAR 8/84 0 environmental requirements. 'this assures PSE&G that the plant design is in accordance with re ulatory requirements, good engineering practices, and good operating and maintenance characteristics. The chief project engineer is also responsible for approving Bechtel bidder's lists and procurement recommendations.
- c. Project construction manager - The project construction manager is responsible for construction and site activities up to fuel load. He directs and coordinates construction activities with Bechtel to ensure the work is being performed in accordance with the terms of the contract, procedures, i drawings, and specifications and within budget and schedule. This also includes reviews of construction manpower use,
- d. Project licensing manager - The project licensing manager is responsible for applying for all necessary licenses. He directs the work of personnel in studies and tasks supporting the licensing efforts. All his activities are conducted in accordance with the project licensing plan.
He is the principal contact with the NRC on licensing issues. He must maintain himself current with licensing requirements and operating experiences, as well as coordinating the development of the final safety analysis report (FSAR).
- e. Project startup manager - The project startup manager is responsible for the development and implementation of the preoperational testing
- _ program. This includes the administrative
- ~ procedures, technical requirements, and personnel resources to ensure a safe startup.
- f. Assistant project manager - The assistant project manager assists the project manager in all phases of the project, but specifically in coordination with other departments. He acts as the project manager E in his absence. .
f L I 13.1-4 Amendment I' b
i i HCGS FSAR 8/84
- g. Manager - Quality Assurance Engineering and construction dmanager - quality assurance engineering and construction is responsible for the direction, control, and documentation of the quality assuranc,e program for HCGS during the design, procurement, fabrication, and construction of the plant.
13.1.1.1.2 Preoperational Activities The design of the Hope Creek advanced control room included a control room co.nplex operability analysis. This was used to finalize the basic design of the main control panels. As part of the analysis, a team of experienced power plant personnel and specialists verified the adequacy and acceptability of system control and monitoring functions. Simulated plant operation was performed using a full-scale pictorial mockup presentation. The human engineering, device and panel visibility, and simplification of operator movements and sequence for normal and abnormal conditions are the basis for optimizing the control room. Further studies are performed associated with improving the information provided the control operators based on a reanalysis of transients, accidents, and the safety parameter display system function for determining the safe status of the reactor core. An independent consultant is used to perform the final humanistic analysis of the control room complex to ensure the highest standards of human factors engineering. In recruiting the staff for Hope Creek, starting 1981-83, PSE&G has used nuclear experienced personnel f rom within the company in key positions, who are supplemented by experienced personnel from outside the company to provide the required depth in plant ,A management and staff. At the time of fuel load, all perso@.1 filling plant organization positions will meet the requirements as identified as ANSI /ANS 3.1 1981. The training of licensed and nonlicensed personnel is outlined in Section 13.2. 13.1-5 Amendment _,. - ,.____-,,_r_ - - ~ . - , , ,
HCGS FSAR 8/84 The development of plans for the preoperational and initial test program are identified in Section 14.2. The preoperational test
. program is directed, coordinated, and implemented by the startup manager of the Hope Creek project team. Station personnel .
provide checkout tests, calibration, and operation of the systems during the test program. The initial testing (Phase III) program is the responsibility of Hope Creek operations. These responsibilities are identified in Section 13.1.2 under the responsibilities of the technical manager. The operating and maintenance programs are in effect to support the preoperational test program ar.d are further i'dentified in Se ction 13.1.2. 13.1.1.1.3 Technical Support for Operations Vice . president - nuclear - As the senior nuclear manager in ; overall charge of the company nuclear program, the vice president
- nuclear provides the management direction and control over the activities of the operating nuclear plants and their needed services and support as shown on Figures 13.1-6a, 13.1-7, 13.1-7a, 13.1-8 and 13.1-8a and as described below.
- a. Assistant Vice President - Nuclear Operations. The assistant Vice President - Nuclear Opertions provides the day-to-day direction and control of the nuclear operations functions directly related to plant operations, maintennnce, outage management and industrial relations.
- b. Assistant Vice President - Nuclear Operations Support. The Assistant Vice President - Nuclear Operations Support provides the day-to-day direction and control of the support functions necessary for the safe and reliable operation of the plants including engineering, licensing and reliability, nuclear fuel technology, methods and systems, public affairs, and personnel affairs.
F 13.1-6 Amendment 1
- HCGS FSAR 8/84
- c. General Manager - Nuclear Quality Assurance. The General Manager - Nuclear Quality Assurance provides the day-to-day direction and control of functions
, which assess the safe operation of*the nuclear stations, quality of work performed by support personnel and compliance of al! departments with OA program requirements, regulatory commitments and other company and governmental policies and regulations,
- d. General Manager - Nuclear Safety Review. The General Manager - Nuclear Safety Review provides management direction and control over on-site and off-site independent safety review functions, including technical staf f work for the Nuclear Safety Advisory Board, an independent committee which provides an overview of Nuclear Department operations for the Vice President - Nuclear.
- e. General Manager - Nuclear Engineering. The General Manager - Nuclear Engineering directs and controls engineering services for operating nuclear plants; provides engineering services for plant modifications and operations / maintenance activities; establishes criteria and specifications for systems and equipment performance; directs and oversees the performance of safety evaluations on all design changes and abnormal plant occurrences.
- f. Managet - Nuclear Licensing and Reliability. The Manger - Nuclear Licensing and Reliability directs and controls all nuclear licensing, fuel design and reliability assessment activities to support operating nuclear plants; coordinates regulatory and environmental program activities and all company involvement wi,th regulatory agencies.
- g. General Manager - Hope Creek Operations. The General Manager - Hope Creek Operations is the senior manager located within the nuclear station and provides management directio and control for the cafe and efficient operation of the station.
- h. General Manager - Nuclear Services. The General Manager - Nuclear Services directs and controls all 13.1-7 Amendment
HCGS FSAR 8/84 nuclear servico functions which include maintenance services, training, site protection, rauiation
. protection services, procurement and material
. control, and emergency preparedness.
- i. Manager - Methods and Systems. The Manager -
Methods and Systems directs and controls the development and implementation of ef fective Nuclear
Deartment-wide services for information systems,
cost and scheduling methods, records management systems and the promulgation of Nuclear Department policies and procedures.
- j. -Public Affairs Manager - Nuclear. The Public Af fairs Manager - Nuclear ^1s responsible for the management and direction of public affairs .
activities for the Nuclear Department and for the preparation, updating and sign-off of the public information section of the emergency plan. He presents the Company's position on relevant public policy or legislative issues,
- k. Personnel Affairs Manager - Nuclear. The Personnel Affairs Manager Nuclear directs and controls the human resources and administration functions for the Nuclear Department which include employee benefits, medical services, employment and placement, equal opportunity activities, employee compensation, management resource development, personnel development, personnel administration and administrative services.
- 1. Manager - Outage Services. The Manager - Outage Services is responsible to manage, direct and control the outage committee in all matters related to the planning, scheduling, conduct and control of utagesp Jesponsible to minimize the outage
-duration with good management and safety practices and to assure that outage activities are in compliance with facility license, Company and p$y governmental regulations..
p p 13.1-8 Amendment I i
~
4" L
HCGS FSAR 8/84
- m. Nuclear Industrial Relations Manager. The Nuclear Industrial Relations Manager is the chief t- interpreter and spokesman for the Nuclear Department
' on all matters pertaining to Company / Union agre ments and management labor relations, and ensures consistent Nuclear Department-wide adherence to Company / Union agreements and good labor relations practices.
- n. Assistant General Manager - Joint Owners and Regulatory Affairs. The Assistant General Manager -
Joint Owners and Regulatory Affairs serves as the chief coordinator and spokesperson for the Nuclear Department on aspects of Nuclear D-spartment pctivities involving Co-owners and State regulatory bodies; assists in the preparation for rate case proceedings; and testifies for the Nuclear Department before the New Jersey Board of Public Utilities and other similar regulatory agencies.
- o. Special Projects Administrator. The Special Projects Administrator provides technical research, writing, liaison and special projects assignments for the Vice President - Nuclear; investigates and reviews nuclear industry and regulatory concerns and recommends appropriate Company responses to the Vice President.
- p. Operations Technical Staff support. The Operations Technical Staf f Support provides the Assistant Vice President - Nuclear Operations with technical review of operations related concerns and handles special inquiries and projects regarding technical operation functions or interfaces.
p Th'goefd
- q. Nuclear Safety Advisor Board. The Nuclear Safety Advisory Boar is a se ior level management oversight co ttee. is charged with prov! ding an overview of the company's nuclear safety program; reviewin the policies and processes to identify issues o rends requiring management attention; and advising he Vice President - Nuclear accordingly.
13.1-9 Amendment
HCGS FSAR 8/84
- r. Manager - Nuclear Maintenance Services - The Manager.
Nuclear Maintenance Services provides the personnel
- and technical expertise to augment the nuclear station mechanical, electrical, and, instrument and control maintenance. This includes the maintenance and technical support of the inservice inspection program, insurance inspection program, and code requirements. He also provides integrated testing of plant modifications.
- s. Manager - Nuclear Site Protection The fanager -
nuclear site protection develops, implements, and maintains a comprehensive program for emergency preparedness designed to protect the health and safety of the public during nuclear plant emergencies; implements and maintains a comprehensive program of security measures of the nuclear station; and develops, implements, and maintains fire protection and industrial safety , programs to meet federal regulations.
- t. Manager - Nuclear Training - The Manager - Nuclear Training is responsible for the training programs for nuclear plant NRC licenses and requalification; provides apprentice and advanced training for personnel in operating, maintenance, chemistry, and radiation protection; and ensures that nuclear training meets industry standards and INPO criteria.
- u. Manager - Radiation Protection
- Services - The Manager - Radiation Protection Services is responsible for the corporate radiation protecticn program to endure personnel exposures and releases to the environment are as low as is reasonably achievable (ALARA); and provides a centralized facility for dosimetry, radiation protection, instrumentation calibration and repair, respirator protection, and laundry services. l
! v. Manager - Nuclear Licensing and Regulation - The Manager - Nuclear Licensing and Regulation is responsible for overall management of liccnsing and regulation activities associated with PSE&G operating nuclear facilities. He manages the preparation, review, and approval of licensing documents and coordination of PSE&G involvement with l 13.1-10 Amendment
e HCGS FSAR 8/84 regulatory agencies and provides licensing direction within PSE&G and to vendor and consultant personnel to ensure that regulatory requirements are met.
- w. Manager-NuclearFuel-TheManageq-NuclearFuell is responsible for providing the nuclear physics, thermal hydraulics, safety and transient analysis expertise to ensure safe and economical use of nuclear fuel. He formulates operating strategies and schedules for nuclear units, provides technical assistance for plant operations pertaining to the reactor core, and develops mathematical computer.
models and monitors core performance. In addition, he evaluates fuel performance and verifies core design with nuclear fuel vendors, as well as prepares design data, specifications, and analyses required for core reload licensing.
- x. Manager - Reliability and Assessment - The Manager-Reliability and Assessment directs the activities of the reliability and assessment group, which performs the review of industry operating experiences including events which occur at PSE&G facilities and disseminates information to the appropriate departments. He provides a technical service in the equipment reliability program. He evaluates the failure data and trends and initiates corrective recommendations to improve equipment reliability.
- y. Assistant General Manger - Nuclear Engineering - The l Assistant General Manager - Nuclear Engineering directs those engineering activities necessary to furnish engineering and design services required to support operating nuclear generating stations.
he provides technical consultation and engineering services for plant modifications, and maintenance. pe also establishes general criteria for systems and-equipment performance, application, and operation in accordance with regulatory and PSE&G requirements. Nuclear engineering responsibilities are delegated as follows, indicatedinz[throughcc. 13.1-11 Amendment i 1
HCGS FSAR 8/84
- z. Manager - Hypy Creek (Salem) Systems Engineering - The Manager - Hope Creek (Salem) Systems Engineering is responsible for providing engineering services necessary to study, design, specify, evaluate, modify, and maintain p s systems for nuclear power production. He p ms systems and plant interaction analyses in s of plant operations, problems, and m ications. He also provides technical direction on process systems, water chemistry, and radioactive waste treatment systems. In addition, he establishes system design criteria and safety classifications and performs safety evaluations for design changes and abnormal plant occurrences, aa. Manager-Mygpanical/ Civil (I&C/ Electrical)
Engineering - The Manager - Mechanical / Civil (I&C/ Electrical) Engineering is responsible for providing engineering services necessary to study, design, specify, evaluate, modify, and maintain plant components and hardware. He establishes component and/or hardware specifications, safety claasifications, and performs detailed engineering for design changes. He evaluates component and/or hardware malfunctions and provides technical direction for corrective action when appropriate and provides technical direction in the development and maintenance of computer process and control systems. He also establishes and maintains plant site arrangements.
. bb. Manager - Nuclear Engineering Design - The Manager -
Nuclear Engineering Design performs detail design and prepares drawings, models, charts, etc.)as . required. He establishes design standards and controls design document distribution and maintains recordst reproduces tracings, prints and documents; and controls microfilming of design documents. He also administers a computerized drafting program. (1) This pcsition is presently titled Manager - Nuclear Systems Engineering. The position will be retitled Salem Systems Engineering and an additional organization titled Hope Creek Systems Eagineering'will be in place prior to fuel load. (2) This position is presently titled Manager - Nuclear Plant Engineering and will be divided into two separate organizations prior to fuel load. 13.1-12 Amendmer.t
c
)
o HCGS FSAR 8/84 cc. . Manager - Nuclear Engineering Control - The Manager
- Nuclear Engineering Control establishes and
- maintains engineering work procedures and job control systems for assigning, monit6 ring, and closing out all work projects within the engineering organizaiton. He establishes work priorities and schedules and coordinates job assignments among engineering organizations. He coordinates and prepares engineering estimates and coordinates implementation of the engineering assurance program.
A breakdown of the nuclear department present and anticipated staffing level is provided in Table 13.1-1. 13.1.1.2 Organization Arrangement , As identified in Section 13.1.1.1, the Hope Creek project is the responsibility of the vice president - engineering and construction, with the project team established to direct nd manage the construction effort until core load. During this period, the nuclear department, as identified in Section 13.1.1.3, will provide technical support and backup for the operating organization. At the time for core load, the nuclear department will be in a position to technically support the f acility during the startup testing program and throughout the life of the plant. This will permit the vice president of engineering and construction to conclude the responsibility for technf(al support of the project. Figure 13.1-3 identifies the engineering and construction department and the Hope Creek project manager. Figure 13.1-4 identifies the engineering department, which provides the technical support to the project team during the construction phase. Figures 13.1-7, 13.1-7a, 13.1-8 and 13.1-8a identify the nuclear department staff providing nuclear service and nuclear support to the facility during startup and throughout the life of the plant. 13.1-13 Amendment
\ .
HCGS FSAR 8/84 13.1.1.3 Qualifications For staffing the technical support organization PSE&G uses qualification requirements similar to those of other major ongineering firms, which consist primarily of individuals having college degrees or.the equivalent in appropriate science or engineering disciplines. In certain instances, technicians who by virtue of formal education, training programs, or experience have acquired special expertise in particular areas, are involved in providing technical support. In keeping with responsible management practices, the capabilities of individuals and necessary supervision are appropriately considered in making personnel assignments. Resumes for the individuals holding these positions are in Table 13.1-la,
- a. Vice President - Nuclear. The Vice President -
Nuclear shall hold a bachelors degree in engineering or related technical discipline generally associated with power production; have training in nuclear science, nuclear power plant operations and maintenance; and have a minimum of eighteen years of progressively more responsible power plant experience, of which at least eight years shall be experience in nuclear power generation and/or related nuclear fields. In addition, the vice President - Nuclear shall be familiar with regulatory requirements and applicable codes and standards.
- b. Assistant Vice President - Nuclear Operations. The 4
Assistant Vice President - Nuclear Operations shall hold a bachelors degree in engineering, science or a related technical discipline generally associated with power production, and have at least sixteen years of experience in progressively more responsible positions in power plant engineering, construction or operation. A minimum of eight years of this experience shall consist of providing day-to-day direction and control of nuclear operation functions directly related to plant operation, maintenance, and/or outage management. In addition, the Assistant Vice President - Nuclear Operations shall be familiar with regulatory requirements, applicable codes and standards and good industrial relations practices, r 13.1-14' Amendment
1 e HCGS FSAR
- 8/84
- f. General Manager - Nuclear Engineering. The General Manager - Nuclear Engineering shall hold a bachelors degree in engineering or science, be a licensed Professional Engineer, and have at least fifteen years experience in progressively more responsible positions in power plant engineering, construction or operation. A minimum of seven years of this experience shall be in nuclear plant construction, engineering, or plant operating experience. In addition, the General Manager - Nuclear Engineering shall be familiar with regulatory requirements and applicable codes and standards.
- g. Manager - Nuclear Licensing and Reliability. The Manager - Nuclear Licensing and Reliability shall hold a bachelors degree in engineering or science and have at least. ten years of experience in power plant engineering, construction, quality assurance or operations. A minimum of five years of this experience shall be nuclear power plant construction, engineering, or plant operating experience. In addition, the Manager - Nuclear Licensing and Reliability shall be familiar with regulatory requirements, the regulatory process, overall plant operation, applicable codes and standards, and quality assurance functions,
- h. General Manager - Hope Creek Operations. The General Manager - Hope Creek Operations or the Assistant General Manager - Hope Creek Operations shall hold a bachelors degree in engineering or a related science and hold an NRC Senior Operator License, (or have held a license or been certified at 'the plant or at an appropriate simulator) and shall have at least fiften years of experience in progressively more responsible positions in power plant engineering, construction, operation, or quality assurance. A minimum of three years of this experience shall be nuclear power plant operating experience.
13.1-16 Amendment
HCGS FSAR 8/84
- i. General Manager - Nuclear Services. The General Manager - Nuclear Services shall hold a bachelors degree in engineering or science and have at least
. fifteen years of experience in progressively more responsible positions in power plant engineering, construction or operation. A minimum of seven years of this experience shall be nuclear power plant construction, engineering or plant operating experience. Familiarity with regulatory requirements and applicable codes and standards is required.
- j. Manager - Methods and Systems. The Manager - Methods and Systems shall hold a bachelors degree in engineering, computer sciences, business administration or a related discipline and have a minimum of ten years of experience in the development and implementation of information systems, including a minimum of five years in responsible supervisory positions.
- k. Public Affairs Manager - Nuclear. The Public Affairs Manager - Nuclear shall hold a bachelors degree in public relations, communication sciences, business, or engineering, and have a minimum of five years of experience in the public relations field.
'This experience shall be in progressively more responsible positions, including supervisory roles, and include at least three years of experience in the nuclear power industry.
- 1. Personnel Affairs Manager - Nuclear. The Personnel Affairs Manager - Nuclear shall hold a bachelors degree in personnel management, business or engineering, and have at least five years of experience in the personnel management field. This experience shall be in progressively more responsible positions including supervisory roles and shall include at least three years of experience in the nuclear power industry.
13.1-17 Amendment
HCGS FSAR 8/84
- m. Manager - Outage Services. The Manager - Outage Services shall hold a bachelors degree in engineering or a related physical science and have at-least ten years of experience in progressively more responsible supervisory positions in power
_ plant maintenance, operations or maintenance engineering support. A minimum of five years of this experience shall be in nuclear power plant operations or operations support. 4 n. Nuclear Industrial Relations Manager. The Nuclear Industrial Relations Manager shall hold a bachelors degree'in industrial and labor relations or M.B.A. with a major in industrial relations, and shall have at least five years of experience in industrial relations with emphasis on grievance processing, arbitration preparation and presentation, and contract negotiation and labor law. O
- o. Manager - Nuclear (Maintenance Services - The Manager
- Nuclear Maintense Services shall hold a bachelors degree in engineering or a related physical science and have at least tengyears experience in progressivelymorer(ponsiblesupervisorypositions in power plant maintenance, operations or maintenance engineering support. A minimum of three years of this experience shall be nuclear power plant maintenance experience. He shall be familiar with regulatory requirements, the regulatory process, overall plant operation, applicable codes
. and standards, quality assurance, non-destructive examination and craft techniques associated with plant maintenance.
- p. . Manager-Nuclear Site Protection - The Manager-Nuclear Site Protection shall hold a bachelor's degree in engineering, science, or associated technical field. He shall have at least 8 years of experience in the nuclear power industry with a strong working knowledge of nuclear plant security, nuclear fire protection, and nuclear emergency preparedness.
13.1-18 Amendment
HCGS FSAR - 8/84
- q. Manager - Nuclear Training - The Manager - Nyclear Training shall hold a bachelor's degree, preferably with an advanced degree in engineering, science, or education. In addition, he shall have training in educational concepts and shall have at least 8 years of appropriate professional experience. The manager of nuclear training, or his designee responsible for the technical content of the licensed operator training programs, shall have at least 3 years of nuclear experience where he was a participant in the operations or training activities of an operating nuclear power plant.
- r. Manager - Radiation Protection Services - Manager -
Radiation Protection Services shall hold a bachelors degree in a science or engineering subject, preferably.related to radiation protection. He shall have 5 years of experience in the nuclear power reactor field. Three years of this experience shall be working with radiological problems at an actual nuclear power facility.
- s. Manager - Nuclear Licensing and Regulation - The Manager - Nuclear Licensing and Regulation shall hold a bachelors degree in engineering or sc'ience.
He shall have a minimum of 10 years of experience in the nuclear industry, of which at least 3 years shall be experience in a licensing organization. He - shall be familiar with regulatory requirements, the regulatory process, overall plant operation, applicable codes and standards, and quality assurance functions. 13.1-19 Amendment
7 e HCGS FSAR . 8/84
- t. Manager - Nuclear Fuel - The Manager - Nuclear Fuel shall hold a bachelor's degree in engineering or science, or have equivalent educational background.
He shall have at least 10 years of experience in progressively more responsible roles of which at least 5 years must be nuclear-related experience. He must have knowledge of the nuclear fuel cycle and experience in nuclear core analysis and nuclear fuel management.
- u. Manager - Reliability and Assessment shall hold a bachelor's degree in engineering or science, or have equivalent educational background. He shall have at least 10 years experience in progressively more responsible positions of which at least 5 years must be nuclear power plant construction, engineering or operations experience,
- v. Assistant General Manager - Nuclear Engineering -
The Assistant General Manager - Nuclear Engineering shall hold a bachelor's degree in ergineering or science and have at least 12 years ;f experience in progressively more responsible and supervisory roles in power plant engineering, construction, or operation. A minimum of 5 years of this experience shall be nuclear plant construction, engineering, or operating experience. Familiarity with regulatory requirements and a licable industry codes and standards is desi able.
- w. Manager-(pgpeCreek) Salem Systems Engineering - The Manager - (Hope Creek)
Salem Systems Engineering shall hold a bachelor's degree in engineering or related physical science and have a minimum of 10 years of nuclear-related experience, including a minimum of 3 years in responsible supervisory positions. This position corresponds to the " Engineer in Charge" as described in Section 4.6.1 of ANSI /ANS-3.1-1978. (3) See Footnote (1), Section 13.1.1.1.3 13.1-20 Amendment
l 4 HCGS FSAR , 8/84
- x. Manager-Mygpanical/ Civil (Isc/ Electrical) [
;- Engineering - The Manager - Mechanical / Civil i t n (IEC/ Electrical) engineering shall hold a bachelor's !
~
e degree in engineering or related physical science and have a minimum of 10 years of nuclear-related i experience including a minimum of 3 years in i D., i responsible supervisory positions. 1 This position corresponds to the " Engineer in
- - Charge" as described in Section 4.6.1 of U. ANSI /ANS-3.1-1978. i
- y. Manager - Nuclear Engineering Design - The Manager Nuclear Engineering Design shall hold a bachelor's degree in engineering or related physical science, or have equivalent related experience with a minimum of 10 years of nuclear power generating facilities experience, including a minimum of 3 years in responsible supervisory positions.
1
- z. Manager - Nuclear Engineering Control. The Manager -
- Nuclear Engineering Control shall hold a bachelors n ' '. ' ' dogree in engineering or related physical science and have a minimum of eight years of nuclear-related
' experience, including a minimum of two years in .
responsible supervisory positions. ! 13.1.2 OPERATING ORGANIZATION
, y ,
- uis section describes the organizational functions and ,
estaponsibilities of the onsite organization, Hope Creek i ope rations . t 13.1.2.1 PLANT ORGA.a riTION The station organization charts for Hope Creek Generating Station . . 3 (HCGS), Figures 13.1-9 through 13.1-13, indicate the title of l each position, the number of personnel assigned, and the c!, positions for which reactor operator and senior reactor operator L.. OL : licenses are required. Table 13.1-2 identifies the schedule for
, assigning personnel to the identified position.
n! r
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" '(4) 'See Footnote (2), Section 13.1.1.1.3
, l
,' 4 t r u" l o 13,1-21 Amendment
8 HCGS FSAR 8/84 13.1.2.2 PLANT PERSONNEL RESPONSIBILITIES AND AUTHORITY The General Manager of Hope Creek Operations is responsiblo for all plant organizational activities. As the senior manager located ae the station, he provides the management direction and control of the day to day operations. In the event of an unexpected contingency, the succession of authority and responsibility for the overall operatioa is in the following orders
- a. Assistant general managor
- b. Technical manager
- c. Operations manager.
13.1.2.2.1 overall Station Managomont The General Manager - Hopo Crook Operations reports directly to the Assistant Vice President - Nuclear Operations, and is responsible for the overall management, direction, and control of station activitt s. In fulfilling thoso responsibilitios he o nd efficient operation of the HCGS. Those ensures functions theincl sfup'o out are not limited te genersi administration, liaison actis ites with regulatory and other agencios, approving and implemon ' rograms and proceduros, and acting on matters pertaining to mpany policios and practicos. He acts as the chairman of the Station Operatione Review Committoo (SORC). Ho is responsiblo for onsuring compliance with the requirements of the technical specifications, operating licenso, and all other applicablo government regulations. The Gonoral Manager - Hope Crook Operations also ensures the station's commitment to the PSE&G operational cuality Assuranco Program by maintaining close liaison with the Station Quality Assuranco Engincor. The Assistant Gonoral Manager - Hopo Crook Operations reports direct 1/ to the Gonoral Managor. Ho assists the Gonoral Managar in all of his principal accountabilition and assumon responsibilitos for station managomont in the Gonoral Managor's abaonco. 13.1-22 Amendmont
i .
. i <..
s HCGS FSAR Ci - 8/84 The Assistant General Manager's functional management responsibilities-include the direction and coordination of the Operations, Technical, Maintenance, and Radiation Protection De partmen ts ' daily activities. He serves as the vice - Chairnan of the SORU and maintains ' contact with the NRC Resident Inspector. - The Office Supervisor also reports directly to the General Manager and is responsible for clerical support; operation of the word processing center; control of plant costs and budgeting; and liaisoit with the Nuclear Service organizations for the control an'd procurement of plant materials, equipment and operating supplies. 13.1.2.2.2 . Operating Department The operating department is responsible for safe and efficient plant operation. The operations manager reports to the assistant general manager and is responsible for managing, directing, and controlling the department activities. The operations manager ,. ensures that plant operation complies with the facility operating license, technical specifications, and all government and company regulations. He ensures that a properly trained, licensed and non-licensed staff is available to provide safe and efficient operation which in turn ensures plant availability and reliability. Administratively, the operations manager is responsible for the approval of all operating procedures and the review of incident
- reports, reportable occurrences, and other correspondence.
The operations manager interfaces with the following managers of nuclear ' depai tment i organizations as mentioned in Section 13.1.1.1.3 in the pertormance of the department activities: i ? u
- r. \ s
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13.1-23 Amendment
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" HCGS FSAR 8/84 a.- Manager - Nuclear Site Protection - To provide emergency preparedness, safety, and fire protection
-coordination
- b. Manager - Nuclear Training - To ensure training of licensed and nonlicensed personnel
- c. . Manager - Nuclear Reliability and Assessment - To establish a criteria of operational assessment and reliability d Manager - Nuclear Licensing and Regulation - To provide licensing and regulatory guidance ,
- e. Manager - Radiation Protection Services - To ensure that plant operation is aligned to ALARA and environmental programs.
.The operations manager is assisted by the operating engineer.
The' operating engineer will assume the authority and responsibility of the department in the absence of the operations manager. . The operating engineer assists the oporations manager
.in the implementation of his responsibilities by directing and controlling the work of the department. Reporting to the operating engineer are the: Senior operating supervisor who provides routine direction to the operating shift; the senior operating support supervisor who oversees radioactive waste management;-and the senior operating technical supervisor who provides technical and administrative support to the department.
l5 The functions of the senior' operating technical supervisor include:
- a. Reviewing incident reports, reportable occurrences, departmental accident reports, and other NRC correspondence
- b. The preparation and maintenance of necessary operating, abnormal, emergency, and other departmental procedures
- c. Implementation and tracking of the safety tagging program, equipment unavailability, and surveillance scheduling.
13.1-24 Amendment i.-
HCGS FSAR g/g4 The functions of the senior operating support supervisor include:
- a. Providing overall waste management program direction to the shift support supervisons in their work
. hssociated with the handling, processing and storing of all process generated radioactive waste.
- b. Ensuring that radwaste activities are in compliance with facility operating license, technical specifications, and government regulations
- c. Development and maintenance of radwaste procedures to ensure that activities are conducted safely and efficiently by trained personnel.
- d. Implementing a program to minimize generation of liquid, solid, and gaseous wastes.
13.1.2.2.3 operating shift supervision Supervision of the shift personnel is under the direction of the senior nuclear shif t supervisor who reports directly to the senior operating supervisor. The senior nuclear shift supervisor "On Duty" is directly responsible for the operation of the unit. He has the authority to take any action necessary, including plant shutdown, accordance with [ approved procedures.[to protect equipment or personnel and to ac During of f-normal hours, he assumes responsibility for all plant functions in the absence of senior plant management. The senior nuclear shift supervisor supervises the operating department shift personnel and inspects equipment to ensure that operations are conducted safely and efficiently in compliance with technical specifications and the operating license. He also reviews and approves completed checkoff lists, logs, and other shift data to detect abnormal trends or potential operating. problems. He approves removal of equipment from service and performance of safety tagging in support of the plant surveillance and maintenance program. 13.1-25 Amendment
1 HCG 3 FSAR 8/84 The senior nuclear shift supervisor is assisted by the nuclear shift supervisor and shift support supervisor. The nuclear shift supervisor assumes the senior nuclear shift supervisors' responsibilities in the event of his unavailability. As assigned, the nuclear shift supervisor reviews procedures which apply to startup, power operation, shutdown, emergency, and abnormal conditions. The nuclear shift supervisor provides direct supervision of the operating crews. The shift support supervisor provides direct supervision to the equipment operators and utility operators and utility operators assigned to radwaste. Personnel qualified as shift technical advisor shall be assigned on shift. The shift technical advisor (STA) may be senior reactor operator (SRO)-licensed. If so, they may function as a nuclear shift supervisor. The STA responsibilities include:
- a. Providing an independent objective assessment concerning plant safety
- b. Providing technical assistance to shift supervision during normal and abnormal conditions
- c. Comparing operating to design parameters during transient or accident conditions to determine adequate core cooling and providing recommendations l to prevent loss of adequate core cooling
- d. Determining critical parameters in the event of instrument failure
- e. Investigating and assessing recommendations of all
( incident reports and reportable occurrences
- f. Evaluating effectiveness of emergency procedures and recommending revisions.
13.1.2.2.4 Licensed Operators Nuclear control operators (NCO) report to the senior nuclear shif t supervisor through the nuclear shif t supervisor and perform all shift operations from the main control room. The NCO is I l ! 13.1-26 Amendment l
l HCGS FSAR 8/84 responsible for manipulating controls for startup, changing electrical output and reactor power, and plant shutdown as required. These functions are in compliance with the facility operating license and technical specifications to ensure safe and ef ficient operations. To meet these requirements, the, licensed operator must:
- a. Remain knowledgeable of all operating, emergency and abnormal procedures
- b. Complete checkoff lists, logs, and other required shift data
- c. Initiate immediate action necessary to maintain the
, plant in a safe condition during normal, abnormal, and emergency operation and shut the reactor down when he determines that the safety of the reactor is in jeopardy or whenever operating parameters exceed reactor protection system setpoints and an automatic shutdown or station response fails to occur.
- d. Routinely observe plant equipment and parameters
- e. Direct the activities of the nonlicensed operators in support of plant operation
- f. Provide an adequate shift turnover to ensure continuity of safe operation.
13.1.2.2.5 Unlicensed operators The equipment operator and utility operator perform routine duties outside of the main control room necessary for safe continuous operation of the plant as directed by the nuclear control operator or nuclear shif t supervisor. Their duties also include: l
- a. Completing checkoff lists, logs, and other shift data
- b. Initiating immediate actions necessary to maintain equipment assigned in a safe condition during normal, abnormal, and emergency operations l 13.1-27 Amendment
1 HCGS FSAR 8/84
- c. Routinely observe equipment assigned
- d. Operating auxiliary equipment as assigned to support plant operations. -
Equipment operators and utility operators assigned to radwaste ' report directly to the shift support supervisor and perform all shift radioactive waste operations required to support plant operations. The shift support supervisor receives administrative and scheduling direction from the senior operating support supervisor. Responsibilities of the operators assigned to radwaste include:
- a. Completing checkoff lists, logs, and other shift data associated with radwaste operations to provide continuous surveillance of the equipment assigned
- b. Manipulating controls, valves, and equipment to support liquid radwaste processing and storing
- c. Initiating immediate actions necessary to maintain radwaste equipment in a safe condition during normal, abnormal, and emergency operations.
Shift electrician, instrumentation and control (I&C) technicians and radiation protection technicians are assigned to shift schedule to report to the nuclear shift supervisor. These personnel perform support functions associated with electrical, I&C, and radiation monitoring disciplines. During normal operation, they are available to perford surveillance, preventative, and corrective maintenance. When periods of emergency or abnormal operating conditions exist, they are available as part of the plant emergency preparedness program for emergency response and technical assistance. 13.1.2.2.6 Technical Department The technical department is responsible for performing functions in the areas of chemistry, I&C, reactor engineering, technical reports and procedures, thermal performance, equipment reliability monitoring and document control. 13.1-28 Amendment
l 1 HCGS FSAR 8/84 The technical manager directs and controls the activities of the department through the chemistry engineer, instrumentation and control engineer, and technical engineer. The technical engineer l assumes authority and responsibility for the department in his absence. The technical manager repbrts to the assistant general manager of operations and is responsible for all activities of the technical department. The technical manager interfaces with the following managers of the nuclear department organizations as mentioned in Section 13.1.1.1.3 in the performance of the department activities:
- a. Manager - Nuclear Fuel - For reactor engineering and the nuclear fuel analysis
- b. Manager - Nuclear Engineering Control - To provide plant modification and technical assistance
- c. Manager - Nuclear Training - To ensure department training and development
- d. Manager - Nuclear Reliability and Assessment - To assess operating experience and reliability
- e. Manager - Nuclear Licensing and Regulation - To coordinate station response to license event reports
- f. Manager - Methods and Systems - To coordinate computer application and software maintenance,
- g. Startup Manager - To coordinate preoperational testing (Phase II) activities.
The startup organization, as defined in Section 14.2, uses the chemistry, I&C, maintenance, and reactor engineering groups during preoperational and startup testing phases. These groups perform sampling and analysis of fluids, tests and calibration of plant-installed instrumentation, initial criticality, physics, and power ascension testing. Individual responsibilities are described below: 13.1-29 Amendment l 1
I I l HCGS FSAR 8/84
- a. Principal startup engineer - The principal startup engineer - testing reports to the startup manager during preoperational testing and then reports to the technical manager during Phase III (initial operations). His responsibility during Phase III is the overall planning and implementation of the
~ testing program, including core load, initial criticality,'and low power physics and power ascension testing. These activities include:
- 1. Procedure preparation and revisions
- 2. Determining manpower support
- 3. Test scheduling 4.- Personnel qualifications
- 5. Analysis of test results
- 6. Test report preparation.
- b. Chemistry engineer - The chemistry engineer is responsible for the development and implementation of the chemistry, radiochemistry and effluent monitoring programs. The senior chemistry supervisor reports to the chemistry engineer and
. assumes authority and responsibility in his absence. The senior chemistry supervisor, through chemistry supervisors, implements the following a'ctivities:
- 1. Sampling of plant fluid systems
- 2. Laboratory analysis
- 3. Result reporting
- 4. Evaluation of laboratory techniques
- 5. Operation of the demineralized water plant
- 6. Maintaining the chemistry of in-plant fluid systems and effluents within established limits.
13.1-30 Amendment
4 o- , l l HCGS FSAR 8/84
- c. Instrumentation and Control Engineer - The I&C
.. Engineer is responsible for the development and implementation of the instrument and control maintenance and surveillance pebgrams. Reporting to the I&C engineer are the senior I&C dupervisors and the-senior engineer I&C staff. The senior I&C supervisor directs the I&C supervisors, the computer supervisor, and the craft workers. The senior engineer - I&C staff directs the I&C staff engineers in support of the line activities and controls the administrative functions of the department. The senior I&C supervisor normally assumes authority and responsibility in the absence of the I&C engineer.
However, the senior engineer - I&C staff may be
; delegated this responsibility directly and also assumes this responsibility when both the I&C engineer and the senior I&C supervisor are absent.
Responsibilities of the group include:
- 1. Preventive maintenance
- 2. Corrective maintenance 4
- 3. Control and calibration of test equipment
- 4. Implementation of design modifications
- 5. Support of initial startup test program (Phase II/III)
- 6. Assurance of adequate procedural support
- 7. Planning and scheduling of department
-activities.
! d. Technical Engineer - The Technical Engineer is responsible for the areas of reactor engineering, technical reports and proc'edures, thermal performance, equipment reliability monitoring and
' testing, and document control. Reporting to the technical engineer are the senior reactor supervisor, senior engineer - technical and the senior engineer technical staff. The senior reactor supervisor assumes authority and responsibility in his absence.
13.1-31 Amendment
i HCGS FSAR 8/84
- e. Senior reactor supervisor - The senior reactor supervisor is responsible for reactor engineering and thermal performance and equipment reliability monitoring. Engineers are assigned to the senior reactor supervisor to develop and implement the details of the programs. The reactor engineering
[ group assists the principal startup engineer in the development and implementation of initial C, crit ality, low power physics and power ascension te programs and provides technical direction to the operations for thermal and nuclear operation of the reactor and initial core loading and refueling operations. The reactor engineering group also monitor, collect, trend, and analyze performance data for systems important to plant efficiency and reliability.
- f. Senior engineer - technical staff - The senior engineer - technical staff is responsible for the administrative progdures, technical responses, and reports leaving th station in support of facility license and review of ope' rating experiences.
Reporting to the senior engineer - technical staf f are the staff engineers and the technical document room supervisor.
- g. Senior engineer - technical - The senior engineer -
technical is responsible for providing support and services to all station departments in the area of computer based information systems. He interfaces with the methods and systems department and maintains the plant process computer sof tware and l works closely with the computer supervisor to maintain the processing computer in op.erable status,
- h. Technical document room supervisor - The Technical document room supervisor directs the operation of the technical document room, which includes centralized control of designated plant documents and records management. He reports to the senior engineer - technical.
-13.1.2.2.7 Maintenance Department The maintenance department is responsible for the performance and monitoring of the electrical and mechanical preventive and corrective maintenance work of the station.
13.1-32 Amendment
e
,HCGS FSAR 8/8'4
- The maintenance manager reports directly to the assistant general
' manager and has the overall responsibility of managing, directing, and controlling all activities of the maintenance department in accordance with the facility license and federal regulations. He is responsible for the development and approval -
of departmental procedures and ensures that department personnel are trained and certified. He is also responsible to ensure that l his department is accomplishing their work safely and efficiently
- in support of plant availability and reliability.
The maintenance manager interfaces with the following nuclear department organizations as mentioned in Section 13.1.1.1.3 concerning maintenance problems:
- a. Manager - Nuclear Maintenance Services - To provide technical expertise for inservice inspection, code and jurisdictional activities, instrument calibration, design change requests (DCRs),
post-design modification testing, and general maintenance support.
- b. Manager Site Maintenance - To provide implementation l of plant betterment items and supervision of contractors support personn
- c. Manager - Procurement and Material Control - To coordinate spare parts and other equipment r purchases,
- d. Manager ' Nuclear Training - To ensure departmental training and development
- e. Manager - Nuclear Engineering and Control - To provide plant modifications and technical support
- f. Manager - Methods and Sygtems - To provide computer l application and budgeting coordination
- g. Startup Manager - To support preoperational testing (Phase II) activities.
L 13.1-33 Amendment i l l i
.s
HCGS FSAR 8/84 Responsibilities of maintenance department personnel are as follows:
. a. Maintenance engineer - The maintenance engineer assists the maintenance manager in the execution of his duties and is responsible to plan, construct, and oversee daily maintenance functions. He is responsible to ensure that identified maintenance activities are completed in a safe, timely, and ef ficient manner. He provides direct supervision to the senior nuclear maintenance supervisors and the senior maintenance planning supervisor. The maintenance engineer assumes the duties of the maintenance manager in his absepce.
Additional responsibilities of the maintenance engineer include the implementation of the following:
- 1. Preventive maintenance program
- 2. Corrective maintenance program
- 3. Equipment and test equipment calibration program
- 4. Department commitment to the as-low-as-is-reasonably-achievable (ALARA) program
- 5. Technical specification surveillance program
- 6. Support of initial startup test program.
- b. Senior nuclear maintenance supervisor - The senior
! nuclear maintenance supervisor is responsible for assisting the maintenance-engineer in planning and executing maintenance repair and. inspection activities. He is respcnsible for the effective use of materials and manpower while conducting maintenance repairs. He directs the activities of - , the nuclear maintenance supervisors and assumes the l authority and responsibilities of the maintenance engineer in his absence.
- 13.1-34 Amendment
HCGS FSAR l 8/84 ' The senior nuclear maintenance supervisor's responsibilities include the following: l
- 1. Scheduling and coordinating department work assignments
- 2. Determining the department training requirements
- 3. Ensuring personnel certification is maintained
- 4. Determining tool requirements,
- c. Senior maintenance planning supervisor - The senior maintenance planning supervisor reports to the maintenance engineer and assists the maintenance I manager in the direction of the department administrative and planning functions. He is l responsible for the maintenance history records, repair ar.d maintenance procedure system (RAMPS),
maintenance procedure preparation, and maintenance planning for both the daily and outage activities. 13.1.2.2.8 Radiation Protection Department The radiation protection department, undar the direction of the radiation protection engineer ensures conduct of the plant
-radiological safety program and the radiological material control programs in accordance with the facility license, government regulations and the nuclear department radiation protection plan. These programs require that personnel exposure to-radiation and releases of radioactive material to the environment are ALARA. The radiation protection program and organization are l described in Section 12.5.
Reporting to the radiation protection engineer are the senior
- - radiation protection supervisor and a staff of supervisors and '
engineers for implementing the following programs:
- a. An effective radiation exposure control and measurement program l
13.1-35 Amendment
1
~ l HCGS FSAR 8/84
- b. Preparation and review of procedures for implementing the ALARA program c.- Surveys of radiatien, surface contamination, and airborne activity to identify locations, operation, and conditions that have potential for significant personnel exposure
- d. The radiation surveillance and personnel exposure tracking program
- e. The emergency response and preparedness manning, procedures, and coordination responsibilities.
- f. An effective ~ radioactive material control and accountability program.
13.1.2.9 Quality Assurance Program The quality assurance / control personnel assigned to the station do not report to onsite management. The quality assurance / control program is described in Chapter 17.2. 13.1.2.3 Operating Shift Crews Shi*t manning is based on an 8-hour shift, 6-days-on/2-days-off schedule (4 shifts) with a fifth shift scheduled for training or requalification. The. actual shift complement for various operational modes is as follows: Operating Not Operating Refueling Position Modes 1-2 __ Mode 4 Mode 5 Senior nuclear shif t 1 1 1 Supervisor (SRO) Nuclear shift supervisor (SRO) l 1 1 supervises fuel handling operation in Refueling Mode 5 STA/ nuclear shift supervisor- 1 - - (STA-qualified) 13.1-36 Amendment b
/
1
l HCGS FSAR . 8/84 Nuclear control 2 2 2
' Operator (RO)
Equipment operators 4 2 2 Shift electrician 1 - - Shift I&C technician 1 - Radiation protection t,echnician 1 1 1 Chemistry technician 1. - - Utility operators - fire brigade 2 2 2 The above manning is in accordance with Supplement No. 1 of NUREG-0737 and , in addition, the following adjunct requirements will be incorporated in the administrative control of shift j manning: ; A licensed senior reactor operator will be in the i a. main control room area at all times when the unit is in Mode 1, 2, or 3.
- b. 14 licensed-reactor operator will be in the main contrei room at all times whenever there is fuel in the reactor.
l c. The licensed senior reactor operator assigned to supervise core alterations in Mode 5 may have no concurrent operational duties.
- d. The qualified shift technical advisor required in Modes 1, 2, and 3 shall a bachelors degree in an engineering discipline and shall have received training as specified in NUREG-0737.
' h t, 13.1-37 Amendment
~, .
HCGS FSAR 8/84
- e. In addition to the radiation protection technician required to be on shift whenever there is fuel in the. reactor, all shift personnel will be trained in e basic radiation protecbion.
Shift hours will be administrative 1y controlled to
- f. . ensure compliance with current NRC policy.
- g. In addition to the specified on-shift fire brigade, the site fire protection program will provide for a
' full-time site fire brigade consisting of fire protection operators and fire fighters trained in firefighting and first aid. Fire brigade training will follow the guidelines of branch technical position CMEB 9.5-1.
13.1.3 QUALIFICATION 'F NUCLEAR PLANT PERSONNEL
.13.1.3.1 Oualification Requirements The qualification requirements for.the onsite plant personnel are in accordance with Regulatory Guide 1.8 and ANSI /ANS 3.1-1981.
The education, experience, and training requirements of the plant personnel-meet the criteria of Section 4 of ANSI /ANS -3.1 at the time of-initial core load. Table 13.1-3 relates to the plant staff positions to the corresponding positions of ANSI /ANS 3.1. The general manager may authorize deviations from a qualification requirement for subordinate positions when the combined education, experience, and managerial competency of an individual is judged suf ficient to endure adequate performance of designated responsibilities. Such judgement will be documented in writing and will not be used to degrade the staff overall qualification. 13.1.3.2 Qualification of Plant Personnel l The resumes of the initial key managerial and supervisory staf f for Hope Creek Operations are identified in Table 13.1-4. 13.1-38 Amendment l
HCGS FSAR 8/84 TABLE 13.1-1 NUCLEAR DEPARTMENT
SUMMARY
STAFFING REPORT On Payroll 1984 Present Approved Anticipated Staffing Staffing Staffing Level Level 12/31/85 VICE PRESIDENT & STAFF 7 4 14 NUCLEAR OPERATIONS SUPPORT Nuclear Engineering 210 251 359 Licensing & Reliability 30 45 75 Methods & Systems 43 73 105 Public Affairs 1 2 5 Personnel Affairs 38 52 54 NUCLEAR QUALITY ASSURANCE 60 93 98 NUCLEAR SAFETY REVIEW 6 8 12 NUCLEAR OPERATIONS Salem Operations 496 558 558 Hope Creek Operations 247 345 370 Nuclear Services 222 325 368 Industrial Rela tions 3 3 3 Outage Services 1 2 Total Department 1363 1760 *2023
* . Includes approxiraately 175 to be transferred from Site Eng in~ee ring , Startup, Construction and Project Management who are currently working on Hope Creek.
13.1-39 Amendment
)
HCES FSAR 8/84 TABLE 13.1-la (Cont) Page of RESUMES OF NUCLEAR DEPARTMENT MANAGEMENT AND TECHNICAL SERVICES AND SUPPORT PERSONNEL TITL_E Vice president - Nuclear Assistant' vice president - nuclear operations Assistant vice president - nuclear operations support General manager - nuclear quality assurance General manager - nuclear safety review General manager - nuclear services General manager - nuclear engineering Assistant general manager - joint owners and regulatory affairs Manager - methods and systems Manager - nuclear licensing and reliability Public affairs manager Personnel affairs manager Manager - outage services Nuclear industrial relations manager Special projects adninistrator ! Manager - nuclear maintenance services Manager - nuclear site protection Manager - nuclear training Manager - radiation protection services Manager - nuclear fuel Manager - Creek (Salen) systems engineering Manager - mecVeivil (I&C/ electrical) engineering ( Manager - nuclear engineering design l Manager - nuclear engineering control L.
HCGS FSAR 8/84 TABLE 13.1-la (Cont) Page of VICE PRSSIDENT - NUCIEAR NAME: Richard A. Uderitt LICENSES AND CERTIFICATES: 1971 New Jersey Stationary Engineer Gold Seal License EDUCATICN: . 1958 Clarkson College , BS Science EXPERIENCE: 1958 - Present Public Service Electric and Gas Company 1981 - Present~ Vice president - nuclear 1980 - 1981 General manager - nuclear production 1977 - 1980' General manager - fuel supply 1975 - 1977- Assistant to general manager - electric production 1973 - 1975 Superintendent - central maintenance 1972 - 1973 Chief engineer - Essex Generating Station 1968 - 1972 Master mechanic - Sewaren Generating Station: Overall responsibility of plant mechanical and electrical maintenance 1968 Operating engineer - Kearny Generating Station: Responsible for daily plant operation
.1965 - 1967 Maintenance supervisor - Sewaren Generating Station 1961 - 1965 Maintenance foreman - Linaen Generating Station: Supervised activities of electricians, boiler repainnen, and machinists in the varied aspects of plant maintenance l
)
IKX3S FSAR 8/84 )
- 1 TABLE 13.1-la (Cont) Page of 4-e- .
1960 - 1961 Assistant engineer - Linden Generating d Station 1958 - 1960 Cadet engineer general office training i program with assignment for familiarization of the company functions 1949 - 1953 U.S. Navy k i d S L e l I l-
HQ;S FSAR 8/84 J TABLE 13.1-la (Cont) Page of ASSISTANT VICE PRPSIDENT - NUCIA%R OPERATIONS SUPPORT NAME: . John T. Boettger , LICENSES AND CERTIFICATES: Professional Engineer, New Jersey EDUCATION: 1955 - 1959 Lehigh University BS, Electrical Engineering 1965' Westinghouse Electric Corporation Pressurizei Water Reactor Seminar O. 1966 General Electric Company _ Boiling Water Reactor Seminar 1968 NUS Corporation Nuclear Powr for Engineers 1969 General Electric Company Fundamentals of Boiling Water Reactor Plant Operations 1969 University of Tennessee Protection Systems for Nuclear Plants 1981 Westinghouse Electric Corporation Pressurized Water Reactor Simulator, ( -Executive Training 1981 Gilbert Associates, Inc l' Executive Seminar on Ouality Assurance '4. b i b l--
F HCES FSAR 8/84 TABLE 13.1-la (Cont) Page of EXPERIENCE:
, 1960 - Present Public Service Electric and Gas Cogpany 1984 - Present Assistant vice president - nuclear operations H support 1981 - Present General manager - nuclear support:
Responsible for engineering, licensing, and fuel design services to support the operation, maintenance, and modific'ations of operating nuclear pcwer generating stations. Overr 7 the performance of independent safety revit.ec of operational activities. 1980 - 1981 General manager - corporate quality assurance: General supervision of the corporate quality assurance department. 'Ihis department interprets regulations, codes, and standards. It also fornulates and approves corporate OA programs and implements assurance functions of these programs. 1972 - 1980 Project manager - Hope Creek: Responsible for the licensing, engineering / design, construction, and startup of two 1100-MWe boiling water reactor power plants 1970 - 1972 Seniar engineer: Responsible for licensing and system analysis for nuclear plant control and protection systems 1960 - 1970 various: Assigments in the engineering department related to the design, construction, and startup of new electrical generating stations 1960 - 1961 Management training program for engineers PROFESSIONAL AFFILIATIONS: Past/present member of ANS, IEEE and EMI Member of IEEE Standards Board Member of Industry Steering Conmittee on PRA Procedures Guide t Past chairman of IEEE/ PES Nuclear Power Engineering Committee l
n- l l I HOGS FSAR 8/84 TABLE 13.1-la (Cont) Page of ASSISTAVr VICE PRESIDENT - NUCLEAR OPERATIONS (Will be provided later) I t k
HOGS FSAR 8/84
- TABLE 13.1-la (Cont) -Page of GENERAL MANAGER - NUCLEAR SERVICES e
NAME:- Henry J. Midura , LICENSES AND CERTIFICATES: Reactor Operator Certification Saxton Experimental Reactor Senior Reactor Operator Salem Unit 1 SOP 2723 EDUCATION: 1955 Rensselaer Polytechnic Institute B.E.E 1969 - 1970- Westinghouse Reactor Operator Training Program - Phase I, II, III (Waltz Mills, saxton, Design Series)
-1972 Startup Training - Surry No. 1 Nuclear Power Plant 1973 Westinghouse - Simulator Training Option II 1974 Westinghouse - Simulator Training Option II EXPERIENCE:
1955 - 1983 Public Service Electric & Gas Company . 1983 - Present General manager - nuclear services at Artificial Island: Responsible for providing technical and manpower (craf t) services to support the operation / maintenance of the Nuclear Units ' that are either beyond the individual station l manpower capabilities or lend themselves to consolidation for improved on-site manpowar use. Specific areas of involvement are as ' follows: radiation protection; site protection including fire, security and emergency preparedness; planning ano e
HO3S FSAR 8/84 TABLE 13.1-la (Cont) Page of scheduling of activities in support of the station requirements; and inservice inspections and nondestructive examinations. The nuclear services department also provides the station with instrument calibration and repair services, overall radioactive waste management, AIARA reviews and maintenance support services and is responsible for the nuclear department material procurement and material control / warehousing services and the coordination and training of nuclear department personnel in conjunction with
- operating the nuclear training center.
1982 - 1983 General manager - lemfperations 1978 - 1981 Manager - Salem Generating Station 1971 - 1978 Chief engineer - Salem Generating Station 1969 - 1971 Master mechanic - Salem Generating Station 1967 - 1968 Master mechanic - Linden Generating Station
,1966 Chief electrician - Essex Generating Station 1965 operating engineer - Sewaren Generating Station 1961 - 1964' Maintenance Supervisor - Mercer Generating Station
'e 1959 - 1960 -Maintenance foreman - Bergen Generating Station 1957 - 1958 Assistant engineer - Linden Generating Station 1955 - 1956 Cadet Engineer Training program
e e HO3S FSAR 8/84 - TABLE 13.1-la (Cont) Page of GENERAL MANAGER - NUCLEAR ENGINEERING NAME: R. A. BurricelIi
, LICENSES AND CERTIFICATES:
Professional Engineer, New Jersey EDUCATIQ4: 1970 - 1973 Butgers University, . Master of Business Administration 1967 - 1969 Rose Hulman Institute of Technology, BS, Mechanical Engineering 1962 - 1964 Newark Chilege of Engineering, M years study toward BSME EXPERIENCE: 1976 - Present Public Service Electric and Gas Cortpany 1981 - Present Manager of methods and administration-nuclear: Responsible for methods and administration activities in the areas of cost and scheduling hunan resources, computer system applications, and management methods and system activities in support of corporate nuclear activities. 1980 - 1981 Manager of emergency preparedness: Responsible for the developnent of emergency preparedness activities in accordance with the requirements of NURfn-0654 to provide for the licensing of Salem Generating Station Unit 2 1979 - 1980 Assistant manager of project control services: Responsible for cost and scheduling activities associated with the construction and operation support of electric generating facilities. I
HOGS FSAR 8/84 TABLE 13.1-la (Cont) Page of 1976 - 1979 Assistant project manager: Fesponsible for
- conpletion of Salem Unit 2, weting for the project manager in his aDsence. Provided direction. for licensing, quality assurance, and startup activities.
Prepared progress reports, conducted weekly project activity rreetimj, and developed estimate of time, hours, and cost. 1976 Project engineer: Responsible for providing projected direction to lead engineering personnel to ensure that engineering activities on the Salen project were accomplished in accordance with projected schedules. Acted for the project manager in his absence and was chief conpany spokesman on licensing matters. Directly supervised licensing coordinator and other project support personnel. 1969 - 1976 Associate engineer: Designed reactor safety systems for the Salem and Newbold Island Nuclear Generating Stations. Administrated cmpany contract with nuclear steam supply system suppliers. Developed a program for nuclear plant protection against industrial sabotage. Developed conceptual layouts and arrangements for new generating facilities. Acted as a liaison between fielo startup persorinel and system design engineers. Evaluated and a, proved design enamjes required by new regulatory requirements.
.'9 b
n l HCGS FSAR 8/84 f TABLE 13.1-1a (Cont) Page of GENERAL MANAGER - NUCLEAR OUALITY ASSURANCS NAME: Charles Peter Johnson EDUCATION 1963 University of Southern California B.S., Industrial Engineering 1965 Completed Navy Otficer's Nuclear Propulsion Training Program 1975 Drexel University MBA, Business Administration 1970 Westinghouse Design Iacture Series - Salem PWR FXPERIENCE: 1970 - Present Public Service Electric and Gas Company 11/1983 - Present Manager - Nuclear Operations Quality Assurance: Responsible for planning, coordinating, directing and overseeing the functional implementation of OAAX projrams dedicated to operation of the Salem and Hope Creek Nuclear Generating Stations. Analyzes the st te-of-the-art concerning Ouality requirements and trends, and interfaces with interdepartzmntal management to ensure attainment of established Quality objectives. 1981 - 1983 Assistant to Vice President - Nuclear, Nuclear Department: Responsible to Vice president for General Office and corporate management liaison on all nuclear matters. Additionally, perform independent reviews of nuclear facilities and special projects. Chairman ot Nuclear Review Board Audits ConTnittee.
$ 4 c [,
G' HCGS FSAR 8/84 TABLE 13.1-la (Cont) Page of 7/1979 - 12/1981 @iclear Plant Engineer, Nuclear Production Department, General Office: Responsible to
, Trianager - Nuclear Operations for evaluation of ~ nuclear plant system operations and performance of design reviews on changes to operating plants and new nuclear plant
- designs.
'4/1977"- 6/1979 Startup Engineer, Engineering and
- Construction Department, Salem Generating Station: Responsible to Project Construction
, r, Manager for all testing activities on Salem No. 2 Unit. As member of Project Team, report to home office Project Manager.
~
Direct group of test engineers (approximately
- 25) whose activities include test planning x' and scheduling; monitoring, assisting, and 7' controlling construction manager's X' + .4 ve'rification test group; inspection and acceptance of all plant systems; and executing detailed preoperational and
, operational sturtup test program.
5/1974 - 3/1977 Startup Engineer, Electric Production Department, Salem Nuclear Generating Station: Fesponsible to Station Manager for developing, plannire, executing and pntrolling Salem No.1 Unit's' test program. _ '_ : Directed. group of test engineers (peak of 44) f whose activities included system inspection t
~'
and ' acceptance, hydrostatic test, flushing
-* , and cleaning, instrunent calibrations and functional testa, system preoperational tests and intergrated operational tests. Primary
.. i 1.r . company liaison with NRC- for system
', inspection and test.
4/1971 - 4/191.4C Associate Engineer, Electric Production D2partment, Salem Nuclear Generating Station:
'f ,
Responsi' ole for the' development of the Salem
.startup test program, including policy manual
~.
and detailed administrative procedures for system' inspection and turnover, writing and
~
~
. executing test procedures, resolution or
, testing neticiencies, and unintenance of
_a , documentation. Defined testiny segucnce and generated detailed schedules (CPt4).
- Conducied manpower study and recormenced stsffing. 'Ihis work was similar to, but more a
preliminary' than that described above.-
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~
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O HOGS FSAR 8/84 TABLE 13.1-la (Cont)' 'Page of 2/1970 - 3/1971 Associate Engineer, Electric Production Department, Linden Generating Station:
- Orientation with company and ccanercial -
electric power generation at conventional steam power plant. Assigned various special projects including dir'ecting boiler chemical cleaning and instructor for boiler operator apprentice training program. 6/1967 - 1/1970 Lieutenant, U.S. Navy. W9apons, Officer aboard nuclear attack submarine, USS SUNFISH (SSN 649): lbasponsible for initial testing, , operation and maintenance of ship's torpedo, fire control and sonar systems during construction and through first year of-operations. Administrator of department consisting of two other officers and twenty-four men. Received Conynendation for highly successful weapon systems trials, acoustic
-trials, and nuclesr weapons inspection.
Engineering Officer of the Watch in naval nuclear power plant during the initial reactor plant test program. .4/1965 - 5/1967 Lieutenant, U.S. Navy, assigned to nuclear attack submarine, USS HAD00 (SSN 604): As Auxiliary Division Officer, responsible to Engineer for operation and maintenance of submarine's hydraulic, air, atmosphere control, and other non-nuciear fluid systems. Related duties included responsibility for effective damage control and ship control procedures, and training and qualification of the crew in these areas. As Supply Officer, responsible for ordering, maintaining and issuing ship's repair parts. Qualifiec as Engineering Of ficer of the Waten, Officer of the Deck, and in Submarines.
I l H MS FSAR -8/84 TABLE 13.1-la (Cont) Page of GENERAL MANAGER - NUCLEArt SAFETY RhVIEd (Will be provided later) l l I e O
l 1 IKDS FSAR - 8/84 TABLE 13.1-la (Cont) Page of ASSISTAlfr GENEDAL MMOGd- JOItfr OWNERS AND REGULMORY AFFAIRS (Will be provided later) I 4 l l. 1 I 1
1 HCI3S FSAR 8/84 ) TABLE 13.1-la (Cont) Page of ASSISTANI GENERAL MANMER - NUCLEAR ENGINEERING NAME: ~ Dennis J. Jagt LICENSES AND CERTIFICATES: Professional Engineer, New Jersey EDUCATION: 1953 - 1957 Newark College of Engineering, BS Mechanical Engineering 1960 Leeds & Northrup Instrtment School 1965 Bailey Meter Analog Control School 1975 General Electric, BWR Fundanentals 1975 PSE&G, Supervisory Training Course t
-- 1975 mles Analys.is Institute /PCEr,G, Problem Analysis and Effective Conmanication of Idea Course 1976 AMR, Project Manager 1977 Rutgers University /PSE&G, Advanced Management Program 1979 PWR Ebndamentals Westinghouse EXPERIENCE:
L 1957 - Present Public Service Electric and Gas Oyrapny 1982 - Present Assistant general manager - nuclear engineering: Responsible for engineering and design services to support operation, maintenance, and modifications of operating nuclear power generating stations
3 HOGS FSAR 8/84 TABLE 13.1-la (Cont) Page of 1979 - 1982 Manager - Salem Project: Responsible for management of engineering and cpnstruction services to support modifications on an
, operating nuclear power generating plant 1976 - 1979 Project manager - Salem Unit 2: Responsible for engineering / design, construction, and startup of an 1100 MWe pressurized water reactor power plant 1976 - 1976 Assistant project manager - Hope Creek:
Responsible for management of engineering / design for two 1100 MWe boiling water reactor power plants 1973 - 1976 Princip 1 engineer: Responsible for engineering of turbine plant and water treatment systems for fossil and nuclear generating facilities 1957 - 1973 Various: Assignments in the engineering departant related to engineering / design of new electric generating stations PROFESSIONAL AFFILIATIONS: Past member of ISA and PMI , Member of American Society of Mechanical Engineers
HCGS FSAR 8/04 , TABLE 13.1-la (Cont) Page of t% NAGER - LICENSING AND RELIAt3ILITY (Will be provided later) e h e-e
r-. HCGS FSAR 8/84 TABLE 13.1-la (Cont) Page of MANAGER - tEDiOOS AND SYbT&lS t%ME: Robert E. Gehret 4 (Will be provided later) l l
h. HQ3S PSAR 8/84 TABLE 13.1-la (Cont) Page of PUBLIC AFFAIRS MANK2ER - NUCLEAR o (Will be provided later) P u..
- + .
- -v, 4..-
I
=~ ' '-
HOGS FSAR 8/84 l 4 '6 % . 1 e , TABLE 13.1-la (Cont) Page of PERSOfMEL AFFAIRS MA M - NUCLEAR NAME:- Stanley M. Kosierowski. s ,
+
(Will be provided later)
~
I 4 1 .; h 9
'i 4
b n a i -
. P ij
- h. ,8 i'
4 i l i I
Y e HC S FSAR 8/84 TABLE 13.1-la (Cont). Page of i NtJCLEAR IUDJb7 RIAL RELATIG4S MANtWER (Will be provided later) L.
. i l
l l I i HCGS FSAR .8/d4 TABLE 13.1-la (Cont) Page of MANAGER - NOCLEAR MAINIENANCE SERVICES NAME:- Frederick Meyer
' LICENSES AND CERTIFICATES:
Engineers License', New Jersey Gold Seal EDUCATION: 1947 - 1949 Attended Montclair State College 1949 '1953 U.S. Merenant Marine Academy, BS, Engineering EXPERIENCE: 1957 - Present Public Service Electric and Gas Conpany 1981 - Present Manager of nuclear site maintenance in nuclear department at Artificial Island: Provide maintenance support and other services to the operation of nuclear plants 1981 Manager of OA operations and maintenance in, general office, corporate quality assurance department: Responsible for directing the OA activities of an operating nuclear plant and supervising OA personnel 1980 - 1981 Mechanical plant enjineer in general office, production department: Provided support and direction to the station's maintenance engineer in resolving problems and inproving the operation of mechanical equipnent - 1974 - 1980 Chief engineer for Bergen Generating Station:
~
Responsible for the sate and etficient operation of the station and the supervision of all operating, performance, and yard department personnel J
^
l HLUS f%M1 8/84 l TABIE 13.1-la (Cont) Page of 1971 - 1974 Maintenance engineer for Bergen Gen *erating Station: Responsible for the proper maintenance of all equipnent at the generating station and the supervision of all maintenance employees 1970 - 1971 Senior engineer in Newark general office: Perfocred various projects to improve the operations or resolve problems associated with generating station equipment 1968 - 1971 Chief electrician for Essey Generating Station: Responsible for the maintenance and operation of all electrical equignent in the generating station and switening station 1967 - 1968 Maintenance foreman and supervisor for Bergen and Essex Generating Stations: Supervised electricians, machinists, boiler repairmen, custodians, etcg in performing station maintenance activities 1961 - 1967 Assistant engineer for Bergen Generating itation production department: Performed 1rious projects in the maintenance, operations, and performance departments 1958 - 1961 Cadet engineer in electric department: Devised program to introduce newly hired engineers to the corporate structure and its functions 1953 - 1957 Marine engineer for United Fruit Company in New York: Licensed engineering watch of ficer, responsible for the maintenance and operations of the ship's boilers, turbines, and auxiliaries 1945 - 1947 Fireman for U.S. Navy: Perfonned various duties in the machinery spaces of U.S. Navy ships
HCIiS FSAR 8/84
-TABLE 13.1-la (Cont) Page of
' e MANMIER - NUCLEAR SITE PfUTECTION
~ NAME: Peter A. Moeller EDUCATION:
1965 U.S. Navy Electronics Technician "A" School 1967 U.S. Navy Nuclear Power Basic and P.rototype 1978. New Jersey Institute of Technology, BS, Industrial Engineering (Cum Laude) FXPERIENCE: 1971 - Present- Public Service Electric and Gas Ocznpany 1982 - Present Manager of nuclear site protection: Responsible for emergency planning nuclear security, fire protection, and industrial safety 1980 - 1982 Responsible for emergency planning and cecurity; developed Salen Dnergency Plan 1978 - 1980 Responsible for all operating nuclear plant licensing; maintained Salem Technical Specifications and interfaced with NRC on licensing matters 1971 - 1978 Assisted in development of the Conduct of Operation section of the Salem FSAR: developed the Salem Security Plan and implementing docisnents; acted as secretary to the Nuclear Review tkurd 1968 - 1971 Reactor. operator on USS Alexander Hamilton
e e HOGS FSAR 8/84 TABLE 13.1-la (Cont) Page of
- MANAGER - NUCLEAR TRAINING ,
NAME: H. Denis Hanson LICENSES AND CERTIFICATES: Reactor operator trainee certification for operation of reactor
,at USN Postgraduate School EDJCATION:
1953 - 1957 U.S. Coast Guard Academy New Inndon, Connect.icut, BS, General Engineering 1962 - 1 % 4 U.S. Naval Postgraduate School , Monterey, California, MS, Physics 1962 - 1964 Nuclear Engineering, Health Physics, and Weapons Effects 1966 George Washington University, Planning, Programing, and Hudgeting Systems 1967 - 1 % 8 Yale University, Administrative Sciences 1968 - 1970 Rensselaer Polytechnical Institute, Harttord, Connecticut, MS, Management Science 1976 Institutes for Academic Deans and Personnel Officers 1979 Personnel Administration Practices for Executives
, tiCGS FSAR -8/84 TABLE 13.1-la (Cont) Page of 0
- 1981 - Present Manager - Nuclear training, PSFJmG:
Responsible for training personnel for three nuclear and six fossil electric generating
, stations for operations, perfonnance, maintenance, and radiation protection departments at all levels. Managed a comprehensive training center and associated staff with an operating budget of S8 million and a capital budget of S30 million, including two control room simulators
-1957 - 1981 Senior coast guard officer: General administration and management. The following is a brief descriptioniot activities performed with the Cgt Guard from 1957 to 1981:
Corporate and division level line and staff assignment is planning, program management, executive assistant, personnel, research and development, operations, and general administration Division officer, executive otticer, and comnanding ' officer responsibilities for both shore and ship facilities Administrative responsibilities for academic division staff of 115 professional (mostly faculty) and 55 tecnnician and clerical personnel Chiet negotiator for management with faculty union; negotiated initial and renewal contract Administered contract empliance, anc trained supervisors and processed grievances Daveloped and coordinated recruiting ef terts, including Em and attinnative action procedures for professional employees Established annual employee counseling and evaluation programs
A i HOGS FSAR 8/84 TABLE 13.1-la (Cont) Page of Provided rewards and discipline as required and appropriate for various personnel categories, effectively hired, fired, and promoted directly reporting staff Served as director of computer center during .i 6-month absence of assigned director Developed operational requirements and coordinated interior design and outfitting for science facility (S5 million) for
l physics, chemistry, and marine science disciplines Responsible for professional and staff developnent for academic division (115 faculty plus support staff)
Assisted in annual institution-wide curriculum review and developnent Promoted from assistsant professor (1967) to full professor (1978) with tenure granted in 1969 Presented leadership develcpment, special skill, and group dyr.amics seminars Taught courses in the global environment, systems technolajy, nuclear and nodern physics, all topics in general physics, and officer professional programs Established requirements and supervised specialized professional training activities for groups of up to 300 people for periods ot
~
3 weeks to over 2 months Served on Admissions Board, Faculty Senate, Academic Council, Planning Board, Executive Board and Budget Coordinatinj Otznmittee 9
.g.-- ,---,, - - . ,
r i. HCGS ESAR 8/84 TABLE 13.1-la (Cont) Page of Responsible for annual budget development including all categories of personnel and funds for eight academic departm nts, library, learning center, cmputer center, and registrar function; maintained 5 year projections on staff and 2 to 15-year plan for major facility project; detennined priorities, allocated resources (including reductions), and monitored operating budget Prepared mid-tenn (2 to 3 years) request for resources for entire institution; developed criteria and priorities for staf f, facilities, and funds; and coordinated a consultant-prepared comprehensive master plan for the Coast Guard Acadent/ Responsible for space allocation /use Responsible toe organizational developwnt; coordinated all phases of division level reorganization and established institution-wide planning board Program manager and responsibility for major training (1500 people per year) and operations (about S25 million per year) activities Presented budget requirements at various - levels, including program support requirements to members of Congress - Developed Ajency Shore Facilities Plan for tertheni California Developed initial Disaster Reliet and Recovery Plan for east coast activities of the Coast Guard, which included response to natural, civil, and nuclear disaster / disorder In charge of disaster relief planning and response for entire Coast Guard Coordinated the Coast Guard / Red Cross agreement for mutual suppcet in times of disaster 1 i I
e HCGS FSAR 8/84 TABLE 13.1-la (Cont) Page of
, Represented the U.S. Department of Treagury and the U.S. Coast Guard in the develognent of Inter-Angency Radiological Defense Plan Developed emergency plans for large facilities; responsible for training various teams associated with potential nuclear disasters Developed operations plans for routine,
- contingency, and wartime activities at district and area (east coast) levels Completed 2-year nuclear engineering effects training, primarily weapons systems and radiation safety / protection Technical advisor for nuclear af fairs for Coast Guard ccmnander ot the eastern and gulf coast region of the US with primary responsibilities in passive defense planning and training, and in disaster control, relief, and recovery Hesponsible for entire Coast Guard's radiological defense and recovery plans and
._ training; represented agency on interservice and interagency comnittees and developed logistics plans, etc Presented nuclear physics, radiation safety, decontamination procedures, etc, seminars, and courses Custodian for radioisotopes and otner nonexempt material requiring licenses
HG;S FSAR 8/t:4 TABLE 13.1-la (Cont) Page of MANAGER - RADIATIG4 PforECTIO4 SERVICES
.NAME: Wayne Linden Britz LICENSFS AND CERTIFICATES: -1966 - 1970 US AEC Reactor Operators License EDUCATION:
1966 US Merchant Marine Acadenry, BS, Conunission as Ensign, USNR; US Merchant Marine, US Coast Guard License as
'Ihird officer 1967 US Merchant Marine Academy, Certificate of Nuclear Power 'Ibchnology 1971 Georgia Institute of Technology MS, Nuclear Engineering, (Atomic Energy Carvnission Followship Program) 1982 Wharton School, University of Pennsylvania, MBA EXPERIENCE:
1980 - Present Manager - radiation protection services, Public Service Electric and Gas Canpany: IMsponsible for corporate radiation protection program to ensure that the
- radiation exposure to personnel and releases of radioactive material to the envirotunent are as low as is reasonaoly achievable (ALARA). Review radiological ef fluent and environmental monitoring system and measurenents to ensure that the stations are Deing operated in a radiological ALARA manner a
HCGS FSAR 8/84 TABLE 13.1-la (Cont) Page of Provide review and audit for Salem and Hope Creek Radiation Protection Programs:to ensure proper and uniform programs. Ensure that radiation protection prograns (including training) reflect contenporary industry practices. Develop and review programs and methods to reduce radiation exposure, reduce costs, and comply with regulations of, state. and federal agencies. Responsible for central radiation protection facilities for Salem and ibpe Creek (dosimetry, AIARA coordination, contaminated laundry, instrument calibration av3 repair, respiratory program, rectrds) Serve as radiation emergency manager in 80F for drills, exercises, anc when the EOF is activated for emergencies. Supervise, train, and ensure readiness at all tinus for the support staff and function required (about 20 persons) 1971 - 1980 US Nuclear Regulatory Comnision, Washington, DC (Headquarters) and Atlanta, Georgia (Regional Office): Experfence in developing and implementing environmental programs. Coordinated and supervised research progra.its with federal laboratories, universities, and consulting firms. Experienced in developing and writing regulations. 'Ibstified in federal courts as expert on environrental program; mrked with legal staff on case and testimony preparation. Represented the NRC on Federal Interagency Task Force for Emergency Preparedness. Detailed to International Atanic Energy Agency to provide assistance to the government of Brazil in developing their nuclear environmental progams. Coauthored several agency pubitcations
1 i HOGS FSAR 8/84 TABLE 13.1-la (Cont) Page of a a
.1966 - 1970 Americam Export Isbrantsen Lines, Inc, New York, New York: Engineering officer, deck officer, and health physicist for a comercial firm operating the Nuclear Ship Savannah, a research and development project for the U.S. Department of Comerce.
Experienced a large variety of the operations
., of a major firm, e.g., routine operation, repair and maintenance, energency operations, scheduling, personnel, and research projects l
HCGS ESAR 8/84 TABLE 13.1-la (Cont) Page of MANAGER - NUCLEAR LICENSING AND REGULATIG4 o NAME: Edwin A. Liden LICENSES AND CERTIFICATES: SRO license SOP-1048, Saxton Power Reactor Facility Newport News Shipbuilding & Dry Dock Co, CVA (N) 65
- Shift Test Ervjineer Oualification Newport News Shipbuilding 7 Dry Dock Co, CG (N) 9 Shif t Test Engineer Qualification U.S. Coast Guard License, Third Assistant Engineer-Steam and Motor Vessels, Oceans, Unlimited Horsepower EDUCATION:
1956 - 1959 South Side Senior High School 1959 - 1963 State University of New York, Maritime College, BS, Marine Engineering 1968 U.S. Public Health Service Course, Management of Radiation Accidents 1973 MIT, Nuclear Powr Reactor Safety Course 1974 PSe&G, Ouality Assurance Orientation 1975 Sales Analysis Institute /PSE&G, Problem Analysis and effective Comunication of Ideas Course 1978 PSE&G, Supervisor / Management Skills Conference 1981 Drake Ream Morin, Inc, Interviewiry Skills Worksnop 1981 Rutgers University /PSE&G, Advanced Management Program
HCGS PSAR 8/84 TABLE 13.1-la (Cont) Page of e 1970 - Present Public Service Electric and Gas Cbnpany 1981 - Present Manager - nuclear licensing and regulation: Provides overall, management of licepsing and
- regulatory activities associated with the conpany's operating nuclear facilities.
Manages the preparation, review, and approval of licensing docunents and coordination of capany involvement with regulatory agencies. Provides licensing direction within the canpany and to vendor and consultant personnel to ensure that regulatory ' _ requirements are met. Alternate member of Corporate Nuclear Review Board 1980 - 1981 Manager - nuclear licensing: Provided overall management of licensing activities associated with the Salem and Hope Creek Generating Stations, including review and approval of licensing docunents and coordination of capany involvement with the NRC's Office of Nuclear Reactor Regulation 1977 - 1980 Project licensing manager: Responsible for
, all licensing activities pertaining to the Unit 2 of the Salem Generating Station 1976 - 1977 Senior engineer 1974 - 1977 Senior staff engineer 1970 -1974 Associate engineer: Participated in the licensing process for the Salem Generating Station, which included preparation of the FSAR, Envirorinental Report, and Safety and Environmental Technical Specifications ,
1967 - 1970 Supervisor of reactor plant services, Saxton Nuclear Experimental Corporation: Held SRO license. Responsibilities included nuclear plant maintenance, performance, health physics, radiochemistry, and radwaste operations. Responsible for all fuel handling operations, e.g., core loading, spent fuel examination, shipping. Extensively involved in training of personnel for RO an SRO examinations e
l HCGS FSAR 8/84 TA8LE 13.1-la (Cont) Page of 1966 - 1967- Staff engineer, Combustion Engineering, Inct Responsible for development and testing of reactor pre re tube conponents for the HWDCR project 3 1963 - 1966 Shif t test engineer, Newport News Shipbuilding and Dry Dock Con Senior shipyard management on shift, responsible for all shipyard activities during refueling, overhaul, and testing operations on the nuclear ship USS Enterprise and USS Iong
, MEh 1963 'Ihird assistant engineer, Military Sea Transportation Service: Licensed waten engineer aboard the USNS Upshur PROFESSIONAL AFFILIATIONS:
Member of /vnerican Nuclear Society r 9
if ' f HOGS FSAR 8/,84 TABLE 13.1-la (Cont) Page of MANMBR - NUCLFAR FUEL , NAME: Elliot S. Rosenfeld Ef11 CATION: New York University, HS, Chemical Ehjineering EXPERIENCE' 1981 - Present Manager - nuclear fuel for PSifW nuclear department: Responsibilities include directing and administering the PSE&G programs for nuclear core performance, core analysis, reload design, nuclear fuel related licensing, technical support to nuclear stations in matters reating to in-core fuel management, and nuclear fuel engineering and safety 1977 - 1981 Nuclear fuel cycle engineer for PSE&G general oftice: Supervised group of erujineerr responsible for development of fuel cycle operating strategy based on system operating and maintenance needs, technical support to nuclear stations in the reactor engineering area, and nuclear fuel related licensing, including reload licensing 1976 - 1977 Staf f Engineer for Jersey Central Powr atxi Light Company (JCP&L) at the Oyster Creek Nuclear Ceneratimj Station Supervised group of enjineers responsible for incore fuel management (functions listed unoer assistant accountability system, and technical advice to operations personnel in ene area of core performance
HGiS FSAR 8/84 TABLE 13.1-la (Lbnt) Page of a (%%UER - RELIABIL11Y AND ASStE94dir e i( (Will tu provided later) 1 0
T H03S FSAR 8/84 TABLE 13.1-la (Cont)~ 'Page of MANAGER - NUCLEAR PLANT ENGINEERING NNIE: lebert L. Gura
- EDUCATION:
1956 - 1960 Stevens Institute of Dchnology, GS, Engineering 1960 - 1965 Stevens Institute of Technology, Master of Management Science 1961 PSFAG , PUR Guide 1961 PSE&G Report Witing 1965 721 Analog Omtrol School 1967 PSEEG Practical Politics 1%7 Bailey 1963 PSEEG CPM 1969 Valve Control 1977 PSE&G PWR Information Course 1979 PSE6G Management Peformance Appraisal System 1981 PSE&G Interviewing Skills - 1981 Hunan Factors Enhancemnt Approach for Nuclear Cbntrol Ibows 1981 IEEE Standard Wrkshop on Hunan Factors and Nuclear Safety
~
12
-i 2
Y HCCS FSAR 8/84 1 4 TABLE 13.1-la (Cont) Page of - i 1960 - Present Public Service Electric and Gas Company 3 N 1982 - Present Manager - nuclear plant engineering, nuclear
- department: Responsible for providing ;
engineering setvices associated with all - engineering disciplines necessary to study, => design, specify, evaluate, modify, and _ maintain plant components and hardware g Senior ergineer/ principal engineer - controls 1973 - 1982 division, engineering and construction 7 department: Fesponsible for direction of - controls engiraers who provided engineering cervices to study design, specify, evaluate, E modify, and maintain control conponents and -! hardware for Salem Nuclear Generating Station ] E 1972 - 1973 Engineer - controls division, engineering and = construction department: Sponsor engineer e for control systems associated with Salem : Nuclear Generating Station; also coordinated ; work effort of other spoasur engineers . g
= -
1969 - 1972 Associate engineer - controls division, engineering and construction department: . Sponsor engineer responsible for design , specification, purchase, and initial _ operation of control equipnent for Salen
- Nuclear Generating Station , a 1966 - 1969 Associate engineer - controls division, engineering and construction departe nt:
]5 Sponsor engineer for control systems at 4 various fossil-fueled generating stations j 1964 - 1966 Assistant engineer - muchanical' division, engineering and construction departnent: 2 various engineering assignments ase:ociated :
with fossil-fueled generating stations 1962 - 1964 Associate engineer - mechanical division, engineering and construction department: [; Assigned to UE&C as a field engineer during 5 construction of Sewaren Unit 5 - 1960 - 1962 Cadet engineer - training program: ) Assigrrnent for familiarization of the company functions s a e unnemmeramuramanameram.emummmerimummmmmmermaremmmuneminummmmmmme-- i
, HCES FSAR ,
8/84 TABLE 13.1-la (Cont) Page of MANMER - ENGINEERITE DESIGN NAME: Alexander 'Ittangson EDUCATION: 1951 Graduated Iaith Technical College, Edinburgh University, BS, General Engineering 1962 - 1967 IEEE special courses in Nuclear Plants, Extra High Voltage, and Ultra High Voltage . 1962 - 1971 New Jersey Institute of Technology and Rutgers University 1967 m stinghouse IMR Fundamentals and Basis Plant Design 1969 CPM Scheduling Course 1974 Report Writing Course 1976 Quality Assurance Course 1976- Supervisory Skills Program 1976 General Electric BWR Basis Plant Design EXPERIENCE: 1958 - Present Public Service Electric and Gas Conpany 1982 - Present Manager - nuclear engineering design . 1967 - Present Wrked on nuclear power generating plants from initial conception through final design for estinghouse PWR and General Electric BWR 1976 - 1982 Assistant Chief design engineer 1973 - 1976 Assistant to Chief design engineer 1969 - 1973 Senior designer
iKUS PSAR 8/84 > TABLE 13.1-la (Cont) Page of 1962 - 1969 Designer: Worked on fossil-fuel generating plant and switching / substation facilities and gas turbine 1958 - 1962 Draftsnan: Worked on fossil-fuel generating plant and switching / substation facilities and gas turbines 1957 - 1958 Consulting engineer: PetecH'hemical Inaustry (DuPont) 1953 - 1957 Junior engineer, design draftsman - electrical / mechanical: Worked on steam and hydroelectric powr generating facilities 1951 - 1953 Engineer office for British Mere ntile Marine: Junior, then senior, marine engineer in complete charge of 2 to 4-hour watches per day over engine, boilers, and all ancillary equipment PROFESSIONAL AFFILIATKNS: Member of Institute Electrical T. Electronics Engineers Senior member of National Society and New Jersey Society of Professional Engineers L
_,y - HOGS FSAR 8/84 TABLE 13.1-la (Cont) Page of MANEER - ENGINEERING OMrHOL ~ e NAME: Timothy N. Taylor ' LICENSES AND CERTIFICATES:
' Professional Engineer, State of New Jersey,19583 EDUCATION:
1964 - 1 % 8 Stevens Institute of Technology, , BS, Mechanical Engineering
~1970 -1973 Stevens Institute of Technology MS, Mechnical Engineering 1971 Rutgers Continuing Engineering Studies, Piping engineering 1971 IEEE, Nuclear Power Plant Design & Environmental Control 1972. ASNUr, Nondestructive Testing 1973 MIT, Nuclear Power Reactor Safety Course 1979 Westinghouse, PWR Information Course 1931 - Present Public Service Electric and Gas Company 1981 - Present Manager - nuclear enginering control, nuclear support department 1980 - 1981 Group head (principal engineer) - Salem nuclear systems group, mechanical division, engineering department 1978 - 1980 Job control engineer - Salem projects division, engineering departnent
I HCGS FSAR 8/84 TABLE 13.1-la (Cont) Page of
- I H
1976 - 1978 Assistant group head - salem nuclear systems group, mechanical division, engineering department 1969 - 1976 Assignment in the piping group - mechanical division, engineering department 1968 - 1969 Cadet engineer - training program: Assignment for familiarization at the cmpany functions Ce e f ,'
.y.,
r e HCGS FSAR 8/84 TABLE 13.1-la (Cont) Page of , SPECIAL PlOJECTS ADMINISTfiAIUR NAME: Richard A. Silverio LICENSES AND CERTIFICATES: New Jersey Blue Seal Operating license Senior Reactor Operator - Salem Station EDUCATI(N 1954 - 1960 Drexel University BS, Electrical Engineering 1970 _W estinghouse reactor generator or certification training program 1971 Observe start-up of H.B. Robinson plant and operations of Connecticut Yankee, Ginna & Surrey nuclear units 1973 - 1984 Senior Reactor Operator - Requalification . Training including simulator training 1981 Executive Technique Cormunications Seminar EXPERIFNCE: 1967 - Present Public Service Electric and Gas Canpany 1984 - Present Special Projects Administrator: responsible to the Vice president - Nuclear for special projects including local governmental atfairs 1982_- 1984 Public Affairs Manager - Nuclear: responsible for handling public information, environmental affairs, governmental atfairs and employee comunication programs. ACr is company spokesperson durirg emergencies 1977 - 1982 Assist nt to Manager - Salem operations , 1974 - 1977 Master Mechanic: responsible for all maintenance operations of the Salem Station 1968 - 1914 Operations Engineer: responsible for startup and normal operation of the Salem Station
{ HCGS FSAR 8/84 TABLE 13.1-la (Cbnt) Page of 1967 - 1969 Engineer: Observed operation at Mercer Generating Station and was sponsor engineer for nuclear system in the Mechanical
~ Engineering Section 1960 - 1967 Held portions of I&C s r engineer and shift test engineer: r sponsible for startup and testing of manual nuclear power plants. New York ship Corp., Camden New Jersey PROFESSIONAL AFFILIATIONS: .
Past/Present member of ANS, IEEE
HCGS FSAR 8/84 TABLE 13.1-la (Cont) 'Page of MANAGER - NUCLEAR SYSTEMS ENGINEERING , NAME: Robert T. Stanley LICENSES AND CERTIFICATES: Professional Engineers, New Jersey EDUCATION: 1964 - 1968 Pratt Insitute BE, Mechanical Engineering 1977 estinghouse Electric Corporation Pressurized Mter Reactor Seminar 1979 PSE&G Management Training Program EXPERIENCE: 1968 - Present Public Service Electric and Gas Company 1984 - Present Manager - Nuclear Systems Engineering Provide Management Control and Direction for the Engineering organization responsible for systems engineering for Nuclear balance of plant and radwaste systems 1982 - 1984 Assistant Manager Nuclear Systems Engineering: assist in management control for engineering review of modifications for NSSS systems, auxilary Systems and Chemical Radwaste Systems rebresendive for the ccnpany Group ontheWstinghouseOwners{#
'b 1979 - 1982 Principal Engineer: Responsible for site engineering group supporting construction on Unit 2 - Salem Generating Station and ,
modifications of Unit 1 Salem Generating Station
HCI;S FSAR 8/84 TABLE 13.1-la (Cont) Page of e 1977 -1979 Senior Engineer: Responsible for mechanical engineering group of the site engineering organization supporting construction of Unit 2 Salem Generation Station. Chairman of the preoperational review cm mittee which reviewed and approved all phase II startup test procedures for Unit 2 1974 - 1977 Isad Engineer: Responsible for solving engineering problems on site, particularly those in the startup area 1968 - 1974 Various assigrunents in engineering departnent both fossil and nuclear related to the design and modification of generating stations. Responsible for flush and cleaning programs for Salem Unit 1
HCGS FSAR 8/84 TABLE 13.1-la (Cont) Page of a MANAGER - OUTAGE SERVICES
- NAME: Gordon E. Lipscy LICENSES AND CERl'IFICATES:
NONE EDUCATION: - 1965 - 1969 University of Minnesota Bachelor Electrical Engineering 1970 Bettis Reactor Engineering School 1971 - 1973 George Washington University Graduate Study - Electrical Engineering Various Project Management & Financial Courses & Seminars EXPERIENCE: 1981 - Present Managenent Analysis Company 1984 Present Manager - Outage services (contractor to PSE&G): Responsible for development of improved outage management planning, scheduling and control systems. AccountaDie for safe and economical completion of all planned nuclear faci y outages.
.1982 -1984 Projepts manager (contractor to 'Ibledo Edisfon)-responsiblefordevelopingand implementing systems and procedures to manage capital modification projects for Davis-Hesse Nuclear Generating Station. Directed a MAC team integrated with client personnel to successfully manage projects and develop client project management skills.
1981 .'982 Outage Manager (contractor to 'Ibledo Edison)
- Responsible for cevelopment of outage planning, control and reporting systems for
- the Davis-Besse Nuclear GeneraJing Station.
Successfully directed an intefgrated outage management organization of client and consultant personnel. Assistec client in selection, training and development of permanent outage management personnel.
I
~
l i HOGS FSAR 8/84 TABLE 13.1-la (Cont) Page of 1979 - 1981 Gulf Oil Corp: girector, configuration management - directpd project control activities of work breakdown structures, contract and subcontract statements of work, baseline tending and change control for the S1.4 billion SRC-II Project to liquefy 6,000 tons coal per day. 1974 - 1979 General Atomic Ompany
>- r 1978 - 1979- Manager, operations and Testing Support -
Directed and manager operatirts/ testing staff of engineers and physicists in start-up, operations and maintenance of catmercial nuclear power station. Responsible for safe operation of S900 million plant and annual operating budget. 1977 - 1978 %pervisor, Testing and Planning - Responsible for and directed planning and performance of comnercial nuclear power plant start-up special tests including camercia ration acceptable to the client, p 1974 -1977 Operations Supervisor / Senior Engineer - lesponsible for day shif t and rotating shif t crew to conduct, direct and epite plant maintenance, outages, modificpations and , design change work in addition to acconpl shing testing and operations for a catme 1 nucigpower station. Responsible for all conaactor and subcontractor work in plant during shif up to 800 craftsnen
. involved.
1969 - 1974 U.S. Navy: Lieutenant accohlished five-year assigrunent w[th Nuclear Navy as lead electrical and I&C engineer for NSSS propulsion plants on USS Nimitz. Trained seniorcrewmegbers. Reported on Rickover's staff. p PROFESSIONAL AFFILIATIO'4S: Member American Nuclear Society Member IEEE Member Project Management Institute l___
7 HCGS FSAR 8/84 TABLE 13.1-2 PLANT STAFF MANNING SCHEDULS Position Status General manager Assigned 1978 Assistant genera l manager Assigned 1981 Technical. manager Assigned 1982 Operation manager Assigned 1981 Maintenance manager Seneduled 1984 Operating engineer Assigned 19d3 Maintenance engineer Assigned 19d2 Radiation protection engineer Assigned 1983 l I&C engineer Assigned 19d2 Chemistry engineer Assigned 1983 Senior nuclear _ shift supervisor. Assigned 1984 Nuclear shift supervisors Assigned L982 Senior nuclear maintenance supervisors Scheduled 1984 Senior I&C supervisor Asslyned 1963 Senior / Lead radiation protection supervisor Schedulec 1984 l Senior chemistry supervisor Scheduled 1964 Senior radiological engineer Seneoulec 1985 Amendment
- - ______---- _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ . _ _ _ . _ ____l
HCGS FSAR TABLE 13.1-3 HOPE CREEK OPERATIONS MANNING CRITERIA Hope Creek Operations Staff Position ANSI /ANS-3.1 Equivalent General manager- Plant manager (1) Assistant general manager Plant manager (1) Technical manager Technical manager (1) Operations manager Operation manager Maintenance manager Maintenance manager (1)
' Technical engineer Technical manager (1)
I&C engineer Instrument & control Chemistry engineer Cnemistry/ radiation enemistry Operating engineer Operation manager (1) Maintenance engineer Maintenance manager Radiation protection engineer Radiation protection (3)(4) Station planning engineer Supervisor not requiring license Office supervisor Supervisor not requiring Itcense Senior operating supervisor Shift supervisor l Nuclear shift technical Shift tecnnical advisor advisors Senior nuclear shift supervisor Snift supervisor Nuclear shitt supervisor Senior oper stor Shift supervisor-engineer Senior operator (2) Nuclear control operator Nonlicensed operator Equipment operator Nonlicensed operator
HCGS FSAR TABL8 13.1-3 (cont) Hope Creek Operations Staff Position ANSI /ANS-3.1 Squivalent .
' Senior operating technical Supervisor not requiring license supervisor-
_ Senior operating support Supervisor not requiring ' license supervisor Senior reactor supervisor Reactor engineering' TDR supervisor Supervisor not requiring license Senior I&C supervisor Supervisor not requiring license I&C supervisor Supervisor not requiring license I&C technician Technician I&C, assistant Senior nuclear maintenance Supervisor not requiring License supervisor Nuclear maintenance supervisor Supervisor not requiring license Electrician Maintenance personnel Machinists Maintenance personnel Boiler repair mechanic Maintenance personnel Station mechanic Maintenance personnel Senior / lead raniation Supervisor not requiring license protect _ ion supervisor (4) Senior , radiological engineer Supervisor not requiring license (4) Radiation protection supervisor Supervisor not requiring license Radiological engineer Staff specialists Radiation protection technician Technician Radiation protection assistant
HCGS FSAR TABLE 13.1-3 (cont) Hope Creek Operations Staff Position ANSI /ANS-3.1 Equivalent Senior chemistry supervisor Supervisor not requiring license Chemistry supervisor Supervisor not requiring license Chemistry technician Technician . Chemistry assistant , (1) The criteria are satisfied when one of the following plant staff meets the position qualifications: General manager or assistant general manager Technical manager or technical engineer Operations manager or operating engineer Maintenance manager or maintenance engineer. (2) . Shift supervisor-engineer is a degreed senior operator who is STA-trained and NRC-licensed as an SRO. (3) RPE shall also meet Regulatory Guide 1.8 criteria. (4) The criteria of Regulatory Guide 1.8 are satisfied when'one of the'tollowing plant staft meets tne position qualifications: Radiation protection engineer or senior / lead radiation protection supervisor, or senior raciological engineer.
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