ML20235L123
| ML20235L123 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 02/21/1989 |
| From: | COMMONWEALTH EDISON CO. |
| To: | |
| Shared Package | |
| ML20235L114 | List: |
| References | |
| NUDOCS 8902270378 | |
| Download: ML20235L123 (46) | |
Text
..
1 1
ATTACHMENT A
' PROPOSED CHANGES TO APPENbIX A IECffBICAL SPECIFICAT10 tis;_01JACILITY QEERATING LICENSES._DE h29 AND NPR_1Q QUAD _CIllES,_ETATIQti 11all_1 11n1L2 Reyised Pages:
'6.1-1 6.1-1 6.1-2 6.1-2 6.1-3 6.1-3 6.1 6.1-4 '
.6.1-5 6.1-5 '
6.1-6 6.1-6 6.1-7 6.1-7 6.1-8 6.1-8 6.1 6.1-9 6.1-10' 6.1-10 6.1 6.1-11 Figure 6.1-1 Figure 6.1-1 Figure
'6.1-2 Figure 6.1-2 6.2 6.2-1 6.2-2 6.2-2 6. 3 - 1_
- 6. 3 -l' 6.4-1
'6.4 /sc1:5428K:33 l
l Q22{ goc
$4 P
QUAD-CITIES DPR-29 6.0 ADMINISTRATIVE CONTROLS
)
6.1 ORGANIZATION, REVIEW, INVESTIGATION, AND AUDIT A.
T;
~'
'un Honoger snaii have overaii iuiinime responsi f/MSE61C safe operation
- it.
Durin e Station l
Manager is unavailable, h this responsibility to an establish e who satisfies the ANSI 8_,
1971
- # :ence requirement: for plant = nager. --
^
B.
The-organicatier chcrt of the corpor;t: management 'hich relctc to the f RWEo I I " t10" Of thiS EI2tiO" 2Ed th0 '0I"1 IOU 0tiO'01 OIS22I23tiOI Ch2rt for cperatien ;f th; ;tati n arc shown in Figuras 5.1-1 and 0.1 2-Tc;pecticc'y.
C.
The _ shift manning for the station shall be as shown in Figure 6.1-3.
I TheFAssistant Superintendent [0peratingi Operating Engineer, Shift l
Engineers, and Shift Foremen shall have a senior operator's license, The Fuel Handling Foreman has a limited Senior Operator's License.
The i.
M M.
YW A ^. :i: tant '!ic: "rc ident and Cencrcl Man;ger-Nuclear Station; on the l
BWe opardiohs corporate level has responsibility for the Fire Protection Program.
The y Assistant SuperintendentlMaintenancelwill be responsible for implementation l of the Fire Protection Program.
A fire brigade of at least 5 members shall be maintained on-site at all times.
This excludes the shift crew necessary for safe shutdown of the plant, and any personnel required for other essential functions during a fire emeroencv.
utietion and Ckmistry 1 D.
Qualifications of the station managemen lo o ygg pgYugl the,";d-Cher Supervisor and the Radiation, hea.perating stari, excluarng l
r ical Technicians, shall N"D.
meet minimum acceptable levels as described in ANSI N18.1, " Selection and Training of Nuclear Power Plant Personnel", dated March 8, 1971.
1 The yed-Cher Supervisor or the Lead Health Physicist shall meet the l
requirements of radiation protection manager of Regulatory Guide 1.8.
bf,,a/
The individual filling the position of ^.::ictant pcrintendent 9,4g,g j/' Tech-iccl Scr"iccc shall meet the minimum acceptable level for
" Technical Manager" as described in Section 4.2.4 of ANSI N18.1-1971.
The Shi f t T-
"# -" ^"
shall have a bachelor's degree or l
t dd3/ f**m equivalent in a scientific or engineering discipline with specific
.En9<4ece
}
training in plant design, and response and analysis of the plant for transients and accidents.
_/ pg The Radiation /Cher/ cal-Technicians /, Technician training progra ar shall have successfully completed the established Radiation / Chemics shall have at least a total of one year of general power plant, hemical, or radiation protection experience, or equivalent
/
h e Radiationghcmical Technicians shall meet the criteria for l
~
.Zh 4.dd/6oh,'" Individuals ~ Qualified in Radiation Protection Procedures", as
[Pede6.h[
described in the D.L. Ziemann (NRC) letter to R. L. Bolger (CECO.)
dated March 15, 1977.
The Radiation /C.".T.ica4 Technician training g progrank consists of the followig 44 ggg 1.
Satisfactory completion of ; L wcek-academic program.
Topi'cs of Ostcaevstbic ccur:
include mathematics, nuclear physics, radioactive 0
decay, chemistry, sampling techniques, reactor coolant parameters, radiation exposure, shielding, biological effects of radiation exposure, radiation survey techniques, personnel monitoring, and emergency procedures 45 wrograa1b 4. //e/r ara.
j 6.1-1 Amendment No. 1
--_-_____a
I INSERT la
.A.
Onsite and=offsite organizations shall be established for unit' operation and corporate management, respectively. The onsite and offsite organizations shall include the positions for activities affecting the safety of the nuclear power plant.
1.
Lines of authority, responsibility,.and communication shall be established and defined for the highest management levels through intermediate levels to=and including all operating organization positions. _ These relationships shall be documented and updated, as appropriate, in the form of organization charts, functional descriptions of department responsibilities and relationships, and job descriptions for key personnel positions, or in.the equivalent forms of documentation. These requirements shall be documented in the Quality Assurance Manual or the Management Plan for Nuclear Operations, Section 3 Organization Authority, Activities: Section 6 Interdepartmental Relationships.
2.
The Station Manager shall be responsible for overall unit safe operation and shall have control over those onsite activities necessary for safe operation and maintenance of the plant.
3.
The Senior Vice President-Nuclear Operations shall have the corporate responsibility for overall plant nuclear safety and shall take any measures needed to ensure acceptable performance of
.the staff in' operating, maintaining, and providing technical support.to the plant to ensure nuclear safety.
4.
The individuals who train the operating staff and those who carry out health physics and quality assurance functions may report to the appropriate onsite managert however, they shall have sufficient organizational freedom to ensure their independence from operating pressures.
INSERT lb The Chemistry Technicians shall have successfully completed the established Chemistry Technician training program.
Both 1517B
o,;
-QUAD-CITIES DPR-29 2.'
Satis' factory performance on a comprehensive examination following completion of~ academic training.
q 3.
On-Shift training'under the supervision of a qualified Rad iatior./CE-"- ',m w W mMrO Tachnirima o4erreer l'
E.
Retraining and repiacerrent training ur Station personnel shall be in accordance with ANSI N18.1,." Selection and Training of Nuclear Power Plant Personnel, dated March 8,1971.
A training program for the' fire brigade shall be maintained under the direction of the Station Fire Marshar and shall meet or exceed the requirements of Section 27 of the NFPA Code-1975 except that training setsions shall be at least' quarterly.
F.
Retraining for licensed operators, senior operators, and senior-ope'rators (limited) shall be conducted at intervals not exceeding 2.
years.
G.
The Review and Investigative Function and the Audit Function of activities affe ting quality during~ facility operations.shall be constituted ana have the responsibilities and authorities outlineri
.gg..
-(dep.ede) below:
1.
The Super"ir of the Offsite Review and Investigative Function I shall be a) pointed by the ^-ir en :nd arrid=t.
ThetAudit
. heqe / m' - Function s1all.be the responsibility of the "=:;;;r cf ^='it3
- ~ "----- and-shall be independent of' operations.
{
@M d38*
J mMi-sde
- a.
Offsite Re wagdInvestigativeFunction Supen M
Q(QA/NS)
.The Su r":::r'of the Offsite Review and Investigative Function shall:
(1) provide directions for the review and investigative function and appoint a senior participant to provide appropriate direction, (2) select each participant JNSOET 8-for this function, (3) select a complement of more than one participant who collectively possess background and.
qualifications in the subject matter under review to provide comprehensive interdisciplinary review coverage under this function, (4) independently review and approve the findings and recommendations developed by personne1~ performing the
- ~ ~
review and investigative function, (5) approve and report in E# b M
a timely manner all findings of noncompliance with NRC requirements to the Station Manager, ^~i-+-' "'-
a--
Cperdshs,Hanager g cr:r:1 ":r n- "ecle:r Stati:n, "r:gr :f Oe:!ity 5.ng
.rurr:0, and thetVice President of Nuclear Operations.
Q4/NS,. Asst 54d/1g During periods when the Sup rei::r.cf Offsite Review and Mc$ - Pressut[MP)
Investigative Function is unavailable, he shall designate this responsibility to an established alternate, who b /,f Pgroms d satisfies the formal training and experience requirements for
'3 bSe55 ^"'Ab th "-
'---'of the Offsite Review and Investigative l
Function.
The responsibilities of the personnel performing this function are stated below.
The Offsite Review and Investigative Function shal1~ review:
i Amendment No. [
6.1-2
[x 3
.t
[e.
. INSERT 2 l
The Manager of QA/NS reports directly to the Chief Executive Officer and has the responsibility to set Corporate Policy for both the areas of Quality Assurance and Nuclear Safety.
Policy is promulgated through a central policy committee directed by the Manager of QA/NS. The Manager of QA/NS has the' responsibility for the performance of periodic audits of each nuclear station and corporate departments to determine that QA/NS policy is being carried out.
/sc1:5428K:27
i
- t" y
QUAD-CITIES OPR-29 e
i 1)
The safety _ evaluations for (1) changes to procedures, equipment, or systems as described in the safety analysis
)
report and (2) tests or experiments completed under the provision of 10 CFR 50.59 to verify that such actions did not constitute an unreviewed safety question.
Proposed changes to the Quality Assurance Program description shall be review d and approved by the Manager of Qu:lity Ass"-ance_ O S.
- 2)
Proposed changes to procedures, equipment or systems which involve an unreviewed safety question as defined in' 10 CFR 50.59.
3)
Proposed tests or experiments which involve an unreviewed safety question defined in 10 CFR 50.59.
S 4)
Proposed changes in Technical Specification NRC operating licenses.
5)
Noncompliance with NRC requirements, or of internal procedures, or instructions causing nuclear safety significance.
6)
Significant operating abnormalities or deviations from normal and expected performance of plant equipment that affect nuclear safety as referred to it by the Onsite Review and Investigative Function.
7)
Reportable events.
8)
All recognized indications of an unanticipated deficiency in some aspect of design or operation of safety related structures, systems, or components.
9)
Review and report findings and recommendations regarding all changes to the Generating Stations Emergency Plan prior to implementation of such change.
s..
thee des [ckhd BW8)
- 10) Review and report findings and recommendations regarding all items referred by the Technical Staff Supervisor, OperabEs,and MP Station Manager, ^.::ict:nt Vi:: "r :id:nt :nd C:ncr:1 1
u.... u m a... e +, u m m,.
..u u. m.,, m. anm.mm cguslob Pr9 rams ord G. L, J '~~~ ~'~~~~"~' ~
~~" ~~ ' ~ ~ ~ ~ '
j r****
MPQuallyQrans and}
- b. s Audit Function g 33,,m,j '
gJone Audit Function shall be the responsibility of the44anageey Of Qu:11ty ^.::ur:nt: independent of the 'ed"ctier ROR oeerde,ns.
02 :rtment.
Such responsibility is delegated to the Oirect r ef Quelity Assurer.ca f:r Oper: ting :nd te th: C ncr:1 Lpi siser Quality A;;;r:n : "cinten:nt: f:r ::inten:nce quality :::gr:n:: ::ti.iti::. Aluelter Qual lty Proyroms Mo-napr.
6.1-3 Amendment No. 1
.....:.a QllAD-CITIES DPR-29 1he Nuclear RuaOy Phyruers Nenye1r-A"+"
shall approve the audit agenda and checklists, the findings and the report of'each audit.
Audits shall be performed in accordance with the Company Quality Assurance Program and Procedures.
Audits shall be performed to assure that safety-related functions are covered within a period.of
-2 years or less as designated below.
1)
Audit of the conformance of facility operation to provisions contained within the Technical Specifications.
and applicable license conditions at least once per year.
2)
Audit of the adherence to procedures, training and qualification of the station staff at least once per year.
3)
Audit of the results of actions taken to correct deficiencies occurring in facility equipment, structures, systems, or methods of operation that affect nuclear safety at least o,ce per 6 months.
4)
Audit of the performance of activities required by the Quality Assurance Program to meet the Criteria of Appendix "B" 10 CFR 50.
5)
Audit of the Facility Emergency Plan and implementing procedures at least once per year.
6)
Audit of the Facility Security Plan and implementing procedures at least once per year.
7)
Audit onsite and offsite reviews.
8)
Audit the Facility Fire Protection Program and implementing procedures at least once per 24 months.
9)
The radiological environmental monitoring program and the results thereof at least once per 12 moni.hs.
- 10) The ODCM and implementing procedures at least once per 24 months.
- 11) The PCP and implementing procedures for solidification of radioactive waste at least once per 24 months.
6.1-4 Amendment No.
l I
i QUAD-CITIES DPR-29
/Yondjer o[ 64 [US, 12)
Report all findings of noncompliance with "R
/
requirements and recommendations and result;, ach audit A l/ F G us / h 8Nrams to the Station Manager, ^.::ict nt "ic: "re c i de r.t c.r.d
)
Pres,[e,,t u opero/wg.
,-C:ncral ", n;ger Nuclear Station, ";nger ;f Qu lity
'N
/ E/CE d
nyonr,nc _ vic, prociannt nf unr,omr nm m t4c m.c 3ng tg M e S e d e M 4 p,.e.3, A f f the D utis: Vice recidentofcenttrhet!en,oreductice, o
Oc/ ear operab/rg,,J 4 CCd EN0 "02Ti"0-l i
OM"iy #f/ Err O'
Authority 624/A/S TheManagerofQulity}.::ur:nceandtheSupervicerofthe l
n ue m om,ieu and investigative C"netier reports to the effefgm Ch:4 r and orecidente Eithec6 Manager of -Quality (pA/MS offseer-E L >="w o, the perci:;r of th: Off:ite 9 view and 4c; :tig:tive unctier has the authority to order unit r
shutdown or request any other action which he deems necessary to avoid unsafe plant conditions.
/pSG'eT 3
=
d.
Records 1)
Reviews, audits, and recommendations shall be documented and distributed as covered in 6.1.G.1.a and 6.1..G.1.b.
2)
Copies of documentation, reports, and correspondence shall be kept on file at the station.
e.
Procedures Written administrative procedures shall be prepared ar.d maintained for the offsite reviews and investigative functions described in Specifications 6.1.G.1.a.
Those procedures shall cover the following:
[p c/hdnf __s=)==
Content and method of submission of presentations to the e
1 Gepew4sw of the Offsite Review and Investigative Function.
2)
Use of committees and consultants.
3)
Review and approval.
4)
Detailed listing of items to be reviewed.
6.1-5 Amendment No.
4
c_-..
{ : ;i.'i:
l 1.
INSERT 3 1The AVP Quality Programs and Assessment reports to the Senior Vice President-Nuclear Operations. 'The AVP Quality Programs and Assessment has~.the' authority to recommend unit shutdown or-request any other action which he deems necessary.to avoid unsafe plant conditions. All such disagreements shall be
' reported immediately to the Manager of QA/NS and the Chief Operating Officer.
/sc1:5428K 28
i.
lci o
' QUAD-CITIES DPR-29 5)
Method of (1) appointing personnel, (2) performing reviews, investigations, (3) reporting. findings and recommendations of reviews and investigations, (4) approving reports, and (5) distributing reports.
6)
Determining satisfactory completion of action required based on approved findings and recommendations reported by personnel performing the review and investigative function.
f.
Personnel 1)
The persons, including consultants, performing the review and investigative function, in addition.to the E : ri::r 1
Sup,nA4nt of the Offsite Review and Investigative Function, shall have expertise in one or more of the following disciplines as appropriate for the subject or subjects i
being reviewed and investigated:
a) nuclear power plant technology, b) reactor operations, c) utility operations, d) power plant design, i
e) reactor engineering, f) radiological safety, g) reactor safety analysis, h) instrumentation and control, i) metallurgy, j) any other appropriate disciplines required by unique characteristics of the facility.
2)
Individuals performing the Review and Investigative Function shall possess a minimum formal training and experience as listed below for each discipline.
a)
Nuclear Power Plant Technology Engineering graduate or equivalent with 5 years experience in the nuclear power field design and/or operations.
b)
Reactor Operations Engineering graduate or equivalent with 5 years experience in nuclear power plant operations.
6.1-6 Amendment No. 1 i
QUAD-CITIES DPR-29 c).
Utility Operations Engineering graduate or equivalent with at least 5
-years of experience in utility operation ac/or engineering.
d)
Power Plant Design Engineering graduate or equivalent with at least 5 years of experience in power plant design and/or -
operation.
e)
Reactor Engineering Engineering graduate or equivalent.
In addition, at least 5 years of experience in nuclear plant engineering, operation, and/or graduate work in nuclear engineering or equivalent in reactor physics is required.
f)
Radiological Safety Engineering graduate,or equivalent with at least 5' years of experience in radiation control and safety.
g)
Reactor-Safety Analysis Engineering graduate or equivalent,'with at least 5 years of experience in nuclear engineering.
h)
Instrumentation and Control Engineering graduate or equivalent with at least 5 years of experience in instrumentation and control design and/or operation.
1)
Metallurgy Engineering graduate or equivaler,t with at least 5 Supend, of. experience in the metallurgical field.
years exlnf 3)
The Epr;f =r of the Offsite Review and Investigative Function shall have experience and training which satisfy ANSI N18.1-1971 requirements for plant managers.
l 1
6.1-7 Amendment No.
c L
i
)
QUAD-CITIES DPR-29 i
2.
The Onsite Review and Investigative Function shall be supervised l
by the Station Manager.
a.
Onsite Review and Investigative Function The Station Manager shall:
(1) provide direction for the Review and Investigative Function and appoint the Technical Staff Supervisor, or other comparably qualified individual as a senior participant to provide appropriate directions; (2) approve participants for this function; (3) assure that a complement of more than one participant who collectively possess background and qualifications in the subject matter i
under review are selected to provide comprehensive interdisciplinary review coverage under this function; (4) l independently review and approve the findings and recommendations developed by personnel performing the Review and Investigative Function; (5) report all findings of noncompliance with NRC requirements, and provide recommendations; Station to the f;;i: tant Vice recident and Cener:1 o
unnager Muclear and the Supervi;;r of th: Off;it 90'/i m: :nd Ir'/ :tigati'/c Functi:n; and (6) submit to the Offsite Review and Investigative Function concurrence in a timely manner, those items described in Specification 6.1.G.1.a which have been approved by the Onsite Review and Investigative Function.
The responsibilities of the Personnel performing this function are stated below:
1)
Reviev of (1) procedures required by Specification 6.2 and changes thereto and (2) any other proposed procedures or changes thereto as determined by the Station Manager to affect nuclear safety.
2)
Review of all proposed tests and experiments that affect nuclear safety.
3)
Review of all proposed changes to the Technical Specifications.
4)
Review of all proposed changes or modifications to plant systems or equipment that affect nuclear safety.
5)
Investigation of all noncompliance with NRC requirements and shall prepare and forward a report covering evaluation and recommendations to prevent recurrence.s th f::ictant-Vic: re fdent and C ncr:1 Manager Nu:! car Ltions and to th; Supervisar af th: Off;it: !! view and In.e:tigativ: Functi'n.
6.1-8 Amendment No. 1 i
4 e
QUAD-CITIES DPR-29 6)
Review of facility operations to detect potential safety hazards.
7)
Performance of special reviews and investigations and reports thereon as requested by the Eu;;r';i:
Offsite Review and Investigative Function. Q:t of thewpenWender 7
8) b/rne.dr eNv/pamk Review of the Station Security Plan and shall submit recommended changes to the.t:i: tant "ic: "r;;ident sad S o,-l@ a,id & AVF
e-
-- i;n;-
f,ggg,y f #"*#' f D.'"/",s"ouoreb a 9)
Review of the Emerge lan and stat on implementing M *"'""*
'd
.M procedures and...,.
...... recommended changes. 4-e-the A(, ddnh4,i /
A::ir+=n+ uno pro c um n+ gnq genergy u3,3ger % 7:37 u, M e m 4;,/,4 2. d [/).
StGtiono-
- 10) Review of reportable events and actions taken to prevent recurrence.
- 11) Review of any unplanned on site release of radioactive material to the environs, including the preparation and forwarding of reports covering evaluation recommendations hee 42 5,ded &>R 1
and disposition of the corrective action to prevent recurrence to the,^.::i;t:nt '!ie: Prc:ident and 0:ncral operofejs y
M;n;;;r N;::::: 5t; tion;, and to the Supervi cr of th i
Offsite Review and Investigative Function.
gdge,d
b.
Authority The Technical Staff Supervisor is responsible to the Station Manager and shall make recommendations in a timely manner in i
all areas of review, investigations, and quality control phases of plant maintenance, operation, and administrative procedures relating to facility operations and shall have the w
authority to request the action necessary to ensure compliance with rules, regulations, and procedures when in his opinion such action is necessary.
The Station Manager shall follow such recommendations or select a course of action that is more conservative regarding safe operation of the facility.
All such disagreements shall be reported immediatelytothe^.::i:tantVicePresident2ndG:nr:!Bw&P/do$s "an;;;r Nuclear St:ti:n; and the Sup;ref:cr of the Offsite Review and Investigative Function.
I i
Supe $ded'b 1
v 6.1-9 AmendmentNo.1p
{
QUAD-CITIES i
DPR-29 l
fe spre/,elandper[
pere c.
Records ca/<m l
1 4./,d.7.a,_
J.
N. 1)
Reports, reviews, investigations, and recommendations 4 Su/2 operdius) shall be documented with copies to the ^.::ict:nt Vice
~
President 1"A c^^^"'
" ' - ' ^ ^ " " - ' ^ - - " " - "
the
- rupen4nM5uper"i r of the Offsite Review and Investigative Function, the Station Manager, and the " n;;;r ;f Quality-
^::ur:nss. A JP c%aMy Proyams ad Asseswent.
2)
Copies of all records and documentation shall be kept on file at the station.
' d.
Procedures Written administrative procedures shall be prepared and staintained for conduct of the Onsite Review and Investigative function.
These procedures shall include the following:
1)
Content and method of submission and presentation to the Station Manager, f;;ictant Vice President :nd Cener:1 B u/E o p e /a n,s u: nager "uclear Stati^nc, and the Eup;rvi-^r of the Offsite Review and Investigative Function.
2)
Use of committees when necessary.
- / #
3)
Review and approval.
4)
Detailed listing of items to be reviewed.
5)
Procedures for administration of the quality control activities.
6)
Assignment of responsibilities.
e.
Personnel 1)
The personnel performing the Onsite Review and Investigative Function, in addition to the Station i
Manager, shall consist of persons having expertise in:
a) nuclear power plant technology, b) reactor operations, c) reactor engineering, d) radiological safety and chemist, e) instrumentation and control, and f) mechanical and electric systems.
)
6.1-10 Amendment No. 1
' [. ;
b 2)'.-. Personnel' performing th'e'Onsite Review and. Investigative'-
~
Function shall meet minimum acceptable levels as.
described in ANSI N18.1':1971,' Sectionsf4.2 and 4.4.
H.
Fi re 'Protec' tion" Prog' ram '
, An independent, fire' protection and 1oss ~ prevention. program inspection i
- and audit'shall be performed at least once per-12 months: utilizing
'either qualified offsite_-licensee personnel or an outside fire protection firm.
An inspection and audit of the fire protection and loss prevention-program shall be performed by'a qualified outside fire consultant at~.
least once per 36 months.
6.1-11 Amendment No. 114
____:_--____-.--___+
e*
i g
QU4D-CITIES DP,E-29 a
- 23. -
1
...l i
nm.
7:-
i:I 1
y3 i
- l-
)
s
.gir 1.1 3:s3 s
- s
_.1 s.
Ea s
l il ug
/:
-E.
1
/_
I I!I l"I s
5
/-
g
/
l
.i l-
-i,L
[
.l I.
l fi I
.g isi
- n I
I !.,
!=
{ll il E5{=
- a. m
.r El I
I u.............,
,En
.a tin
/
lll ss
[ ]
8 1*g
T g
4
~
g-E.
.:.v.
,c... g3 1
i er I
s:
.=,i:
c,
= g!,
=1 g
i
- 1 i
,e 1
i=
,1 2
i
{j g!: }il a
x i
=_
sir ;\\,
e
' s
,8 %
i
= i.a
-[s.: s,
=
i t!!
T.
I11g i :::
.~:.s
- I.1:
s '....\\. l i'i si 'i ~I vg t
I
=I::s g ej l
r v
s, s
/s I I ll g
I I
/
ll I '.
I I
- s \\ l ii s.i I
'. s 1
sk I
I l C. f.
- I,3 i
.I 1g I-I e,
s
- s
-i ep II 18
/ :g!
l-i I
l 5 i
- . T
\\T.
.il; g!
- e gl 7- !! I il3 iii e
si i ie8 f
8 1
sg{
3el 8
z-
/.
........g.
i i iII i
/__
^
'"s I
I
-l- !!
I il I I 3
_J -j j
i rI *{
g j
[I I
l I
I ai s
i i
T-T 3
=g1 1
i g
g
-as I
a g
gll
!j...J
~
- {
s
[ t FIGURE 6.1-1 I
v.g g
"g
- 00 " " ^."_^.* : 0 01.::=*0!!
Amendaient No. 1 bE(E7F,.S
"~~"
S MD A
G T
N N
I E
V D
IllI IIll l ll i I I lll QR N
A E E
R P T
T U yS N
I R
NO' E
P 1 I E S I
U C I V I llI I IIll l 1li l I
F R F E C
O P 3
U I
NS 1
V R
R S
s R
6 O
E T
T N
x E
s
/
T S
N F A D E e a A
E F T E N r r N
I D S I A S Lil I I N
I u g
$ G g o D
N E T
I N
N i r R
E C S S E
F P O
T I
S O
N V A
R i C I
R MO
. n
\\
E S o
t" E
H I L
S i
C V r t A
L 1II I l I lNlIi / R a c I
I S D E h e C
A P C t NA T
R U o
N N
S g r I
A L
nP F
T C O
i e S E R
n I T T R r r N
N O oi S
OS H F S
C I A
V t e C
iI I l l l
\\
lll 1 I y
Y R i h T E i t g,
S I P h
E L U S g T[
I F
A S
" n I
F U
i A
Q e et T R s e n
- R D P S O n s e N
S e
m A D L I c, e U
A V i t l Q
1 I C R L f p
m I E i
N P s h i H U s
'r r
C S E
o r o T
t ef a p S
r
. e N
e rl O
p eb O b i I
T T
ms A R N
R
- r u n E S D
F E io n o L O E
T E p
R I N
II I N
n r s I
5 e o e V
E H
I L R S G S F R N
A E G
E I
P I
R U R N GS N R T S E
I S
P T I
E 0
0 U
U A o T 5 D
T I S R
- III I l l 1 I I A N 5
N N
E S R
I 5 I
E T P E G D
N O P N N
A S
O E E
T T
R T
S N
O N
I F A S S F T E I I
S II A S l I l l O R S
R V II S
S P A
T I S S T E 1
5 A
U S
NO I
T H
C C
U S
E N
D T
T H
O N
N l I lll R
E F A R
F T A T P
D
- N
- I I A S M
E T I I E S S N C S
N N
A A
I R A I
E N R C P E E I I S N l I I I i l l l 1 l I T R U T S T A C I
T A H E N H L
A E
T S
C R
I I
S E N T A S
lI l l l S H A
A C M EM l
o a
' esceccio 6 ose OPR-29 M2NfMUw SM?r? MANM7Nd CHAP?s CONDITION OF ONE UNIT (No Fuel in Second Unit)
License Initial Fuel Loading Cold Snutdown or Aoove Cold Category or During Refueling Refueling Shutdown Shutdown senior Operator License 2
1 2
Operator i
License 2
2 3
Rad. Prot. Man 3
3 1
mon-Licensed (As Required) 1 2
ShifL Technical Advisor mont Required None Required l'
CONDITION OF SECOND UNIT (One Unit at Hot shutdown or at Power)
License Initial Fuel Leading Cold shutcown or Above Cold Category or During Refueling Refueling shutdown shutdown 5enior" Operator License 2
2 2
Operator
- License 3'
3 3
ead. Prot. Man I
i 1
e non-Ltcensed 3+ ( As esquires) 3 4
$nifL Technical Advisor 1
1 1
i l
CokDITIon OF SECOND UNIT (One Unit at Cold shutdown er Refueling Shutdowh)
License Initial Fuel Lossing Cold snutocam or Aoove Cold Category or During Refueling Refueling shutdoun Shutdown.
Senior a Operator License 3
1 2
i operator" License 3
2 3
Rae. Prot. Man i
i I
mon-Licensed 3+ (As Required) 3 3
Sntft Technical Advisor None Required None Required 1
- Assunes each individual is licensed on each facility. During initial fuel leading er during refueling, one senior engineer (Itaited license) will supervise fuel handling.
f shif t crew composition may be less than the minimwe requirements for a period of time not to exceed 2 r ours in order to acconnegate unexpected absence of on duty shif t crew memoors provided immediate action is taken to restore the shif t crew composition to within the minimum requirenants of Figure 6.1-3.
Figure 4.1 3 Amendment No. 114 F-L 1-
4 QUAD-CITIES j
DPR-29 1
1 6.2 PLANT OPERATING PROCEDURES 1
A.
Detailed written procedures, including applicable checkoff lists covering items listed below shall be prepared, approved, and adhered to:
1.
Normal startup, operation, and shutdown of the reactor, and other systems ^and components involving nuclear safety of the facility.
2.
Refueling operations.
- 3.. Actions to be taken to correct specific and foreseen potential malfunctions of-systems or components, including responses to alarms, suspected primary system leaks, and abnormal reactivity changes.
- 4.. Emergency conditions invol'ving potential or actual release of radioactivity
" Generating Station Emergency Plan" and station emergency and abnormal procedures.
5.
Instrumentation operation which could have an effect on the safety of the facility.
6.
Preventive and corrective maintenance operations which could have an effect on the safety of the facility.
7.
Surveillance and testing requirements.
8.
Tests and experiments.
9.
Procedure to ensure iafe shutdown of the plant.
10.
Station Security Plan and implementation procedures.
11.
Fire Protection Program implementation.
12.
ODCM implementation.
w-13.. PCP implementation.
$44 1
14.
Working hours of the Shift Engineer,.... = Control Room J
Engineer, Shift Foreman and the Nuclear Station Operator job classifications such that the heavy use of overtime is not routinely required.
6.2-1 Amendment No. 1
QUAD-CITIES DPR-29 6.2 PLANT OPERATING PROCEDURES B.
Radiation control procedures shall be maintained, made available to all station personnel, and adhered to.
The procedures shall show permissible radiation exposure and shall be consistent with the requirements of 10 CFR 20.
This radiation protection program shall be
, a,, 455,5bf3, organized to meet the requirements of 10 CFR 20.
Su(eoden4#
- C.
1.
Procedures for items identified in Specification 6.2.A and 6.2.B and
,. 4 any changes to such procedures shall be reviewed and approved by the g g/
Technical Staff Su]ervisor, "- ^~"+
' Superintendent, and depart-ment head responsi]le for the activity performed.
At least one person approvingeachoftheaboveproceduresshallholdavalidsenior operator s license.
In addition, these procedures and changes thereto must have authorization by-a-Station c" cr nt:nt nt before i
being implemented.
g h,yl 2
7 Work and instruction type procedures which implement approved pj4ssMad 1
maintenance or modification procedures shall be approved and I g F -@
authorityhasbeenprovidedbygStationSupernt:ntnt.
d authorized by the ^.::t. t up t.
ntenance%where the wri i
The
" Maintenance Modification Procedure" utilized for safety related work shall be so approved only if procedures referenced in the
" Maintenance Modification Procedure " have been approved as required by 6.2.A.
Procedures which do not fall within the requirement of 6.2.A or 6.2.B may be approved by the Department Heads.
D.
Temporary changes to procedures 6.2.A and 6.2.B above may be made provided:
1.
The intent of the original procedure is not altered.
2.
The change is approved by two members of the plant management staff, at least one of whom holds a Senior Reactor Operator's license on the unit affected.
3.
The change is documented, reviewed on the On-Site Review and Investigative Function, and approved by the Station Manager within 14 days of implementation.
E.
Drills of the emergency procedures described in Specification 6.2.A shall be conducted in accordance with the GSEP manual.
/
6.2-2 Amendment Na.
4
QUAD-CITIES DPR-29
<6.3 REPORTABLE EVENT ACTION A.
The following actions shall be taken for Reportable Events:
1.
The Commission shall be notified and a report submitted pursuant to the requirements of Section 50.73 of 10 CFR Part 50.
2.
Each Reportable Event shall be reviewed by the On-Site Review Committee, and the results of this review shall be submitted to l
the Off-Site Review and Investigative Function and to the l
^: ictant Vice President end General Manager, Nuckcr Stetivo.
4 Gwe operahons.
l
~.
6.3-1 Amendment No. 114
QUAD-CITIES DPR-29 6.4 ACTION TO BE TAKEN IN THE EVENT A SAFETY LIMIT IS EXCEEDED If a safety limit is exceeded, the reactor shall be shut down immediately, and reactor operation shall not be resumed until authorized by the NRC.
The conditions of shutdown shall be promptly reported to the ^::4:t:nt Vice T
I President - " 0:ncra! 4: nager Nuclear Station or his designated alternate.
1 3 gg
,f'g"4# l/
The incident shall be reviewed pursuant to Specifications 6.1.G.1.a and 6.1.G.2.a and a separate report for each occurrence shall be prepared in t
~
accordance with Specification 6.3.A.1.
I i
i l
1 l
6.4-1 Amendment No. 114 L _-.
-QUAD-CITIES DPR-30 6.0 ADMINISTRATIVE CONTROLS 6.1 ORGANIZATION, REVIEW, INVESTIGATION, AND. AUDIT A.
Onsite and offsite organizations shall b? established for unit operation and corporate management, respectively. The onsite and offsite organizations shall include the positions for activities affecting the safety of the nuclear power plant.
i 1.
Lines of authority, responsibility, and communication shall be established and defined for the highest management levels through intermediate levels to and including all operating organization j
positions. These relationships shall be documented and updated, as appropriate, in the form of organization charts, functional descriptions of department responsibilities and relationships, and job descriptions for key personnel positions, or in the equivalent forms of documentation. These requirements shall be documented in the Quality Assurance Manual or the Management Plan for Nuclear Operations, Section 3 Organization Authority, Act'vities: Section 6 Interdepartmental Relationships.
2.
The Station Manager shall be responsible for overall unit safe operation and shall have control over those onsite activities necessary for safe operation and maintenance of the plant.
3.
The Senior Vice President-Nuclear Operations shall have the corporate responsibility foc overall plant nuclear safety and shall take any measures needed to ensure acceptable performance of the staff in operating, maintaining, and providing technical support to the plant to ensure nuclear safety.
l 4.
The individuals who train the operating staf f and those who carry out health physics and quality assurance functions may report to the appropriate onsite manager; however, they shall have sufficient organizational freedom to ensure their independence from operating pressures.
B.
DELETED.
C.
The shift manning for the ste. tion shall be as shown in Figure 6.1-3.
The Operating Assistant Superintendent, Operating Engineer, Shift
{
Engineers, and Shift Foremen shall have a senior operator's license.
[
The Fuel Handling Foreman has a limited Senior Operator's License. The Vice President BWR Operations on the corporate level has responsibility for the Fire Protection Program. The Maintenance Assistant Superintendent will be responsible for implementation of the Fire Protection Program.
A fire brigade of at least 5 members shall be l
maintained on-site at all times.
This excludes the shift crew necessary for sale shutdown of the plant, and any personnel required l
for other essential functions during a fire emergency.
l l
1512B 6.1-1 Amendment No.
l l
L_- _ -_
j yg.x l
-QUAD-CITIES i
!j l ~
DPR-30 i
D.
QualificatlJns,of the station management:and operating staff, excluding,
the Health Physics.Se vices Supervisor and.the Radiation Protection and
' Chemistry Technicians, shall meet minimum acceptable levels.asi described in ANSI N18.1,1" Selection'and Training of Nuclear Power Plant..
Personnel", dated March 8, 1971 7 The Health Physics Services Supervisor or the. Lead Health Physicist shall meet the requirements of -
l
. radiation. protection manager of Regulatory Guide 1.8..
The individual
.. filling the position of Technical Superintendent shall meet'the minimum
.[
L..
acceptable level for " Technical Manager".as described.in-Section 4.2.4
)
'of ANSI N18.1-1971.
The Shift Control Noom Engineer shall have a l.
bachelor's' degree or equivalent..In a' scientific or engineering,
' discipline with specific training in plant design,- and. response'and-analysis of.the plant for transients and' accidents.
The Radiation Protection Technicians shall h' ave successfully, completed the established Radiation Protection Technician training program. The Chemistry Technicians shall have successfully completed the established-Chemistry Technician training program.. Both shall have at least a total of one' year.of general power plant, chemical, or radiatien protection expe ience, or equivalent training.
In addition, the.
Radiation' Protection Technicians shall meet the criteria for-l
~
'" Individuals Qualified in Radiation Protection Procedures",'as described In'the D.L.
Ziemann (NRC) letter to R.L. Bolger (CECO.) dated March 15, 1977.- The Radiation Protection or Chemistry Technician
]
training program consists of the following:
1.
Satisfactory completion of an academic program. Topics of these courses include mathematics, nuclear physics, radioactive decay, chemistry, sampling techniques, reactor coolant parameters, radiation' exposure, shleiding, biological effects of radiation exposure, radiation survey techniques, personnel monitoring, and emergency procedures, as appropriate to their area.
l 2.
Satisfactory performance on a comprehensive examination following completion of academic training.
3.
On-Shif t training under the supervision of a quallfled Radiation -
Protection or Chemistry Technician.
j E.
Retraining and replacement training of Station personnel shall be in accordance with ANSI N18.1, " Selection and Training of Nuclear Power Plant Personnel", dated March 8, 1971.
1 A training program for the fire brigade shall be maintained under the direction of the Station Fire Marshal and shall meet or exceed the requirements of Section 27 of the NFPA Code-1975 except that training
' sessions shall be at least quarterly.
F.
Retraining for licensed operators, senior operators, and senior operators (limit ed) shall be conducted at intervals not exceeding 2 years.
1 i
I 1512B 6.1-2 Amendment No.
.g
[.
i le {
QUAD-CITIES.
DPR-30 G.
The Review and Investigative Function-and the Audit Function of' activities affecting' quality during facility operations shall-be constituted and have the, responsibilities and authorities. outlined below 1.
The Superintendent of the Offsite. Review and Investigative Function shall be appointed by the Manager of Quality-Assurance / Nuclear' Safety (QA/NS)..The Corporate Audit' Function shall be the responsibility of the Manager of Quality Assurance / Nuclear Safety (QA/NS) operations.
and shall be independent of The Manager of QA/NS reports directly to the-Chief Executive Officer and has the responsibility to set Corporate. Policy for-both the areas of Quality Assurance end. Nuclear Safety.
Policy is promulgated through a central policy committee directed by the Manager of QA/NS.
The Manager of QA/NS has the' responsibility for the performance of periodic audits of each nuclear station and corporate departments to determine that QA/NS policy is being.
carried out.
a.
Offsite Review and Investigative Function The Superintendent of the Offsite Review and Investigative Function shall (1) provide directions for the review and investigative function and appoint a senior participant to.
provide appropriate direction, (2) select each participant for this function, (3) select a complement of more than one participant who collectively possess background and l
qualifications in the subject matter under review to provide comprehensive interdisciplinary review coverage under this function, (4) Independently review and approve the findings l-and recommendations developed by personnel performing the review and investigative function, (5) approve and report in a timely manner all findings of noncompliance with NRC requirements to the Station Manager, Vice President BWR Operations, Manager QA/NS, Assistant Vice President (AVP)
Quality Programs and Assessment, and the Senior Vice President of Nuclear Operations.
During periods when the Superintendent of Offsite Review and Investigative Function la unavailable, he shall designate this responsibility to an established alternate, who satisfies the formal training and experience requirements for the Superintendent of the Offsite l
Review and Investigative Function. The responsibilities of the personnc1 performing this function are stated below. The Offsite Review and Investigative Function shall review:
15128 6.1-3 Amenanent No.
e.s l'?
QUAD-CITIES:
DPR-30 1)' The. safety evaluations for (1) changes to procedures, L
equipment, or systems as described in the: safety analysis report and (2)-tests or experiments completed under'the-provision of 10 CFR 50.59.to verify.that s'uch actions did:
~
not constitute an unreviewed safety, question.
Proposed changes to the Quality Assurance Program description shall be reviewed'and' approved by the Manager of QA/NS.
l 2)
Proposed changes to procedures, equipment or. systems which involve an unreviewed safety question as; defined in
- 3) Proposed tests or experiments which involve an unreviewed safety question defined in'10 CFR 50.59.
i
- 4) Proposed' changes in Technical Specification NRC operating licenses.
' 5 )'
Noncompliance with NRC requirements, or of internal procedures, or instructions causing nuclear safety significance.
6)
Significant operating abnormalities or deviations from normal and expected performance of plant equipment that affect nuclear safety as referred to it by the Onsite Review and Investigative Function.
7)
Reportable events.
8)
All recognized indications of an unanticipated deficiency in some aspect of design or operation of safety-related structures, systems, or components.
9)
Review and report findings and recommendations regarding all changes to the Generating Stations Emergency Plan prior to implementation of such change.
- 10) Review and report findings and recommendations regarding all items referred by the Technical Staff Supervisor, Station Manager, Vice President BWR Operations, and AVP Quality Programs and Assessment, b.
Station Audit Function
)
The Station Audit Function shall be the responsibility of the AVP Quality Programs and Assessment independent of BWR l
Operations.
Such responsibility is delegated to the Nuclear Quality Programs Manager.
I i
l l
1512D 6.1-4 Amendment No.
--___________-_____O
QUAD-CITIES DPR-30 The Nuclear. Quality Programs Manager shall approve the audit agenda and checklists, _the findings and the report of each audit.
Audits shall be performed in accordance with the Company. Quality Assurance Program and Procedures. Audits shall be performed to assure that safety-related functions are covered within a period of 2 years or less as designated below.
- 1) Audit of the conformance of facility operation to provisions contained within the Technical Specifications and applicable license conditions at least once per year.
- 2) Audit of the adherence to procedures, training and qualification of the station staff at least once per year.
- 3) Audit of the results of actions taken to correct deficiencies occurring in facility equipment, structures, systems, or methods of operation that affect nuclear safety at least once per 6 months.
- 4) Audit of the performance of activities required by the Quality Assurance Program to meet the Criteria of Appendix "B" 10 CFR 50.
5)
Audit of the Facility Emergency Plan and implementing procedures at least once per year.
6)
Audit of the Facility Security Plan and implementing procedures at least once per year.
7)
Audit onsite and offsite reviews.
i 8)
Audit the Facility Fire Protection Program and implementing procedures at least once per 24 months.
- 9) The radiological environmental monitoring program and the f
results thereof at least once per 12 months.
j
- 10) The ODCM and implementing procedures at least once per 24 months.
- 11) The PCP and implementing procedures for solidification of radioactive waste at least once per 24 months.
l
- 12) Report all findings of noncompliance with NRC requirements and recommendations and results of each audit to the Station Manager, Manager of QA/NS, AVP Quality Programs and Assessment, Vice President BWR Operations, the Senior Vice President-Nuclear Operations, and the Chief Operating Officer.
1512D 6.1-5 Amendment No.
[.:2;
.s
(;
Y QUAD-CITIES
- DPR-30 ll l
c.
Authority Thol Manager of QA/NS reports to the: Chief Executive Officer.
The Manager of QA/NS has the authority to orderLunit' shutdown or. request any other action which.he deems.necessary to avoid unsafe plant conditions.
The AVP Quality Programs and Assessment reports to the Senior Vice President-Nuclear Operations. 'The AVP Quality Programs and Assessment has the authority to' recommend' unit shutdown or request any other action which he deems necessary to avoid unsafe plant conditionta.
All such disagreements shall be reported immediately to the Manager of QA/NS and the Chief Operating Officer.
d.
Records 1)' Reviews, audits, and recommendations shall be documented and distributed as covered in 6.1.G.1.a and 6.1.G.1.b.
- 2) Copies of documentation, reports, and correspondence shall be kept on file at the station.
e.
Procedures Written administrative procedures shall be prepared land.
maintained for the offsite reviews and investigative functions described in Specifications 6.1.G.1.a.
Those procedures shall cover the following:
- 1) Content and method of submission of presentations to the Super 3ntendent of the Offsite Review and Investigative Function.
- 2) Use of committees and consultants.
- 3) Review and approval.
- 4) Detailed listing of items to be reviewed.
- 5) Method of (1) appointing personnel, (2) performing reviews, investigations, (3) reporting findings and recommendations of reviews and investigations, (4) approving reports, and (5) distributing reports.
- 6) Determining satisfactory completion of action required I
based on approved findings and recommendations reported by personnel performing the review and investigative l
function.
l 1512B 6.1-6 knendment No.
h
.n QUAD-CITIES DPR-30 s.
('
i f.
Personnel
- 1) The persons, including consultants, performing the review and investigative function, in addition to the Superintendent of the Offsite Review and Investigative l
Function, shall have expertise in one or more of the following disciplines as appropriate for the subject or subjects being reviewed and investigated:
a) nuclear power plant' technology, b) reactor operations, c) utility operations, d) power plant design, e) reactor engineering, f) radiological safsty, g) reactor safety analysis, h) instrumentation and control,
- 1) metallurgy, j) any other appropriate disciplines required by unique characteristics of the facility.
2)
Individuals performing the Review and Investigative Function shall possess a minimum formal training and experience as listed below for each discipline.
a) Nuclear Power Plant Technology Engineering graduate or equivalent with 5 years experience in the nuclear power field design and/or operations.
b) Reactor Operations Engineering graduate or equivalent with 5 years experience in nuclear power plant operations.
l c) Utility Operations Engineering graduate or equivalent with at least 5 years of experience in utility operation and/or engineering.
d) Power Plant Design Engineering graduace or equivalent with at least 5 years of experience in power plant design and/or operation, e) Reactor Engineering Engineering graduate or equivalent.
In addition, at least 5 years of experience in nuclear plant engineering, operation, and/or graduate work in nuclear engineering or equivalent in reactor physics is required.
1512B 6.1-7 Amendment No.
1 QUAD-CITIES DPR-30 1
i'-
I f) Radiological Safety Engineering graduate or equivalent with' at least 5 -
j.
years.of experience in radiation control and' safety..
g g) Reactor Safety Analysis ni i~
Engineering graduate or equivalent,- with at least 5
]{
_ years'of experience in nuclear engineering.
l l i" j.
h). Instrumentation and Control i
ii Engineering graduate 'or eqttivalent with at least 5
,.ji years of. experience in instrumentation and control b
design and/or operation.
~1)
Metallurgy Engineering graduate or equivalent with at least 5 years of experience in the metallurgical fleid.
- 3) The Superintendent of the Offsite Review and l
Investigative Function shall have experience.and training which satisfy ANSI N18.1 1971 requirements for plant managers.
2.
The Onsite Review and Investigative Function shall be supervised by the Station Manager.
a.
Onsite Review and Investigative Function The Station Manager shall:
(1) provide direction for the
' Review and. Investigative Function and appoint the Technical Staff Supervisor, or other comparably qualified individual'as a senior participant to provide appropriate directions;.(2) l approve participants for this function; (3) assure that a complement.of more than one participant who collectively possess background and qualifications in the subject matter l
under review are selected to provide comprehensive interdisciplinary review coverage under this function; (4) independently review and approve the findings and recommendations developed by personne1' performing the Review and Investigative Function; (5) report all findings of noncompliance with 3RC requirements, and provide recommendations; and (6) submit to the Offsite Review and Investigative Function concurrence in a timely manner, those items described in Specification 6.1.G.1.a which have been approved by the Onsite Review and Investigative function.
The responsibilities of the Personnel performing this function are stated below 1512B 6.1-8 Amendment No.
- j.
.~a.
QUAD-CITIES DPR-30
- 1) Review of (1) procedures required by Specification 6.2 and changes thereto and (2).any other proposed procedures or changes thereto as determined by.the Station Manager r
to affect nuclear anfety.
- 2) Review of all proposed tests and experiments that affect nuclear safety.
3)
Review of all proposed changes to the Technical Specifications.
4)
Review of all. proposed changes or modifications to plant systems or equipment that affect nuclear safety.
5)
Investigation of all noncompliance with NRC requirements and shall prepare and forward a report covering evaluation and recommendations to prevent recurrence..
.6)
' Review of facility operations to detect potential safety hazards.
7)
Performance of special reviews and investigations and reports thereon as requested by the Superintendent of the
'l Offsite Review and Investigative Function.
8)
Review of the Station Security Plan and shall submit recommended changes to the Director of Corporate-Security and the AVP-Quality Programs and Assessment in lieu of distribution in accordance with 6.1.G.2.c.(1).
9)
Review of the Emergency Plan and station implementing procedures and identification of recommended changes.
- 10) Review of reportable events and actions taken to prevent recurrence.
- 11) Review of any unplanned on-site release of radioactive material to the environs, including the preparation and forwarding of reports covering' evaluation recommendations and disposition of the corrective action to prevent recurrence to the Vice President BWR Operations, and to the Superintendent of the Offsite Review and Investigative Function.
1512B 6.1-9 Amendment No.
L____-______.
+
.s~w a=
~
QUAD-CITIES l DPR130 ir b.
Authority The Technical' Staff Supervisorcis responsible to the Station Manager and shall make recommendations.in a timely-manner in all-areas of review, investigations, and quality; control l-phases of plant maintenance,; operation, and administrative procedures relating to facility operations and shall have the
~
authority to request the action necessary to ensure compliance with rules, regulations, and procedures when in his' opinion such action is necessary. The Station Manager shall follow suchLrecommendations or select azcourse of action that'is more_ conservative regarding safe operationfor the facility.
All such disagreements shall befreported-immediately'to the Vice President BWR Operations and the Superintendent of the Offsite Review and Investigative Function.
c.
Records
'1)
Reports, reviews, investigations, and recommendations prepared and performed for Specification 6.1.G.2.a. shall be documented with copies to the Vice. President BWR Operations, the Superintendent of the Offsite' Review and Investigative Function, the Station Manager,-and the AVP Quality Programs and' Assessment.
- 2) Copies of all records and documentation'shall be kept on file at the station.
d.
Procedures Written administrative procedures shall be prepared and-maintained for conduct of the Onsite Review and Investigative function. These procedures shall include the.following:
- 1) Content and method of submission and presentation to the Station Manager, Vice President BWR Operations, and the Superintendent of the Offsite Review and Investigative Function.
- 2) Use of committees when necessary.
- 3) Review and approval.
- 4) Detailed listing of items to be reviewed.
- 5) Procedures for administration of the quality control activities.
- 6) Assignment of responsibilities, e.
Personnel 1512B 6.1-10 Amendment tio.
a____________________________
.m
- e.
s i
-i u l
, QUAD-CITIES r
~
DPR-30 1). The personnel performing the Onsite Review'and J
Investigative Function, In addition:to.the Station Manager, shall consist.of persons havingl expertise' ins
-l.
.a) nuclear power plant technology, b)- reactor operations, c) reactor engineering, d) radiological safety and chemist,
,e) instrumentation and control, and f) ' mechanical and electric. systems.
- 2) Personnel performing the Onsite Review and Investigative.
Function shall meet minimum acceptable levels as described in ANSI N18.1-1971, Sections 4;2 and 4.4.
H.
Fire Protection Program An independent fire protection and loss prevention program inspection and audit shall,be performed at least once per 12 months utilizing either qualified,offsite licensee personnel or an outside fire protection firm.
An inspection and audit of the fire. protection and loss prevention program shall be performed by a qualified outside fireiconsultant at least once per 36 months.
1512B 6.1-11 Amendment No.
l
c-_-.______
I
<-e.
h 1
1 :.
OUAD-CITIES DPR-30
+
l l
1.
i l
l
)
I 1
I l
l 1
1 Figure 6.1-1 DELETED 1512D
i QUAD-CITIES DPR-30 l
l FIGURS 6.1-2 1512B DELETED Amendment No.
o
.y;
.l
}3 '
QUAD-CITIES
}
DPR-30 6.2.
PLANT OPERATING PROCEDURES A.
Detailed written proceisres, including applicable checkoff'11sts covering items listed below shall be prepared, approved, and adhered to:
~
- 1. 1 Normal startup, operation, and shutdown of the reactor, and other systems and components involving nuclear safety of the facility.
2.
Refueling operations..
3.
Actions:to be taken to' correct specific and foreseen potential-malfunctions of systems or components, including responses.to alarms,. suspected. primary system leaks, and abnorma1' reactivity changes.
4.
Emergency conditions involving potential or-actual release of;
~
radioactivity
" Generating Station Emergency Plan"~and station emergency and abnormal procedures.
5.
Instrumentation operation which could have an effect on the safety
~ of the facility.
6.- freventive and corrective maintenance operations which could have.
an effect on the safety.of the facility.
7.
Surveillance and. testing requirements.
8..
Tests.and experiments.
9.
Procedure to ensure safe shutdown of the plant.
10.
Station Security Plan and implementation procedures.
11.
Fire Protection Program implementation.
12.
ODCM implementation.
13.
PCP implementation.
l
- 14.. Working hours of the Shift Engineer, Shift Control Room Engineer, l
l Shift Foreman and the Nuclear Station Operator job classifications such that the heavy use of overtime is not routinely required.
I 1513B/
6.2-1 Ame ndine n t Ho.
..)
3 QUAD-CITIES DPR-30 6.2 PLANT OPERATING PROCEDURES' lB. -
Radiation control procedures shall be maintained, made available to al' station' personnel, and adhered to.
The procedures shall show permissible radiation expcsure and shall be_ consistent with the requirements of 10 CFR 20.
This radiation protection program shall be.
organized to meet the requirements of 10 CFR 20.
C.
1.
Procedures for items identified.in Specification 6.2.A and 6.2.B.
and any changes to such procedures shall be reviewed and approved by the Technical Staff Supervisor, an Assistant Superintendent or Technical Superintendent, and department head responsible for the activity performed. At least one person approving each of the above procedures shall hold a valid senior operator's license.
In addition, these procedures and changes.thereto must have authorization by the Station Manager before being implemented.
2.
Work and instruction type procedures which implement approved' maintenance or modification procedures shall be approved and authorized by the Maintenance Assistant Superintendent-where the written authority has been provided by the Station Manager. The
" Maintenance Modification Procedure" utilized for safety related work shall be so approved only if procedures referenced in the
" Maintenance Modification Procedure " have been approved as required by 6.2.A.
Procedures which lo not fall within the requirement of 6.2.A or 6.2.B may be. approved by the Department Heads.
D.
Temporary changes to procedures 6.2.A and 6.2.B above may be made provided:
1.
The intent of the. original procedure is not altered.
2.
The change is approved by two members of the plant management staf f, at least one of whom holds a Senior Reactor Operator's license on the unit affected.
3.
The change is documented, reviewed on the On-Site Review and Investigative Function, and approved by the Station Manager within 14 days of implementation.
E.
Drills of the emergency procedures described in Specification 6.2.A shall be conducted in accordance with the GSEP manual.
1513B/
6.2-2 Amendment No.
=
7JAD-CITIES DPR-30 6.3 REPORTABLE EVENT ACTION A.
The following actions shall be taken for Reportable Events:
1.
The Commission shall be notified and a report submitted pursuant to the requirements of Section 50.73 of 10CFR Part 50.
2.
Each Reportable Event shall be reviewed by the On-Site Review.
Committee, and the results of this review shall be submitted to the Off-Site Review and Investigative Function and to the Vice President BWR Operations.
i l
l I
1514B 6.3-1 Arna n ' na n t tio.
a
. +
a QUAD-CITIES DPR-30 6.4 ACTION TO BE TAKEN IN THE EVENT A SAFETY LIMIT IS EXCEEDED l
If a safety limit is txceeded, the reactor shall be shut down immediately, and reactor operation shall not be resumed until authorized by the NRC.
The
(
conditions of shutdown shall be promptly reported to the Vice President BWR Operations or his designated alternate. The incident shall be reviewed
{
pursuant to Specifications 6.1.G.1.a and 6.1.G.2.a and a separate report for j
each occurrence shall be prepared in accordance with Specification 6.3.A.1.
l 1
i i
l l
l 1515B 6.4-1 Ame ndmen t-No.
l I
,o-s ATTACHMEETJ UETb1 LED-DESCBlE219U_NULSwgg l
/sc1:5428K:34 1
'.w
.c j
SUMMARY
OF CHANGES l
1 I
This proposed change includes revisions to Section 6 of Unit One and Two Technical Specifications (TS) that are desired to reflect Generic Letter 88-06 recommendations and the corporate and station reorganizations.
Generic Letter 88-06 proposed methods to delete the organizational charts currently contained in TS.
The removal of organization charts is a line item improvement that the NRC will review and approve quickly if the proposal conforms to-the guidance provided'in the Generic Letter. Therefore, in addition to deleting the organizational charts contained in Figures 6.1 (Corporate Organization) and Figure 6.1-2 (Station Organization), the following statements are being added (as recommended by the Generic Letter):
A.
Onsite and offsite organizations shall be established for. unit operation and corporate management, respectively. The onsite and offsite organizations shall include the positions for activities affecting the safety of the nuclear power plant.
1.
Linec of authority, responsibility, and communication shall be established and defined for the highest management levels through intermediate levels to and including all operating organization positions. These relationships shall be documented and updated, as appropriate, in the form of organization charts, functional descriptions of department responsibilities and relationships, and job descriptions for key personnel positions, or in the. equivalent forms of documentation. These requirements shall be documented in the Quality Assurance Manual or the Management Plan for Nuclear Operations, Section 3 Organization Authority, Activities: Section 6 Interdepartmental Relationships.
2.
The Station Manager shall be responsible for overall unit safe operation and shall have control over those onsite activities necessary for safe operation and maintenance of the plant.
3.
The Senior Vice President-Nuclear Operations shall have the corporate responsibility for overall plant nuclear safety and shall take any measures needed to ensure acceptable performance of the staff in operating, maintaining, and providing technical support to the plant to ensure nuclear safety.
4.
The individuals who train the operating staff and those who carry out health physics and quality assurance functions may report to the appropriate onsite manager; however, they shal? have sufficient organizational freedom to ensure their independence from operating pressures.
The changes noted above satisfy the guidance of Generic Letter 88-06.
The following summary provides a list of other changes that are being proposed to support the corporate and station reorganization. This list also contains other minor changes that have been identified as being necessary:
1.
" Assistant Vice President and General Manager Nuclear Stations" to "nc e_Pierti de at_RWILRps r a t i o ns ".
1516D L____________
am -
L 2.
" Assistant Superintendent Maintenance" to " Maintenance Assistant Supe 11DLRndRnt".
3.
" Rad Chem Supervisor" to " Health Physica Services SupgrylanI".
4.
" Radiation / Chemical Technicians"-to "Radiatian_RInte.ctinn and Chergistry leshnicians". This change also references the two different training programs that exist for Radiation Protection Technicians'and Chemistry Technicians.
5.
" Assistant' Superintendent-Technical Services" to,"Tenhainal Superintendent".
6.
" Shift Technical Advisor" to " Shift Control Room Engineer".
7.
" Supervisor of the Of fsite Review" to "S.gperintendent of the_Qifsite Review".
8.
The Superintendent in Item 7 above shall be appointed by the "ManageI Rf_DU Allty_ As1MIanCBZllurle_Ar_Sa f e ty ( OA /N S ) " rather than by the
" Chairman and President".
9.
Approving and reporting of all findings of noncompliance with NRC requirements will. now be to the "Yice Presideut_RWJL9peratippst MARA9 eI_.OAIN Et Ag g i s t a n t V i c e P r e s ident_.] AVE.LQg glity,.EIngrpmg__gnd ASEeSSment.,_and_the_Henior Vice EI151 dent _HMRleAt_DpetBliQRS" rather than " Assistant Vice President and General Manager Nuclear Stations, Manager of Quality Assurance and the Vice President of Nuclear Operations".
- 10. The station audit function shall now be the responsibility of the " AVE' Quality ErnVIAma_and Asssisment" rather than the " Manager of Quality Assurance". This is independent of "RW.R_DP.er_ationa" rather than the
" Production Department".
This responsibility can be delegated to the
" Nuclear Quality Programs Manager".
- 11. A typographical error in item 6.1.G.I.b.12 was identified: "gi" should be added between the words "results each".
- 12. As part of the audit function, all findings of noncompliance with NRC requirements...... shall be reported to "...... the Manager _9LRAIN3t the Xics_Etenident__pWR_Op. erat 1QpauAVI Quality Programs _and AEAeElmeDtuthe_ Senior V1gg. Presidant_Hunlemt_QpsImilo.pru_ AnILthe Chie f_OpeIAtlag_.QI11ser". This ta instead of "... Assistant Vice President and General Manager Nuclear Stations, Manager of Quality Assurance, Vice President of Nuclear Operations and to the Executive Vice President of Construction, Production, and Engineering".
- 13. The Manager of QA/NS reports to the "ChieLEKeguti.yB_Q111sel". This is instead of to the " Chairman and President".
- 14. The Manager of QA/NS has the authority to order unit shutdown. This is instead of the Manager of Quality Assurance or the Supervisor of Offsite Review.
15168 '!
l
, _... *.. +
15.'The'AVP Quality' Programs and Assessments reports to the Senior Vice
]
~
President Nuclear Operationy,. He_has the authority to recommend unit 4
shutdown.
If disagreements occur, they shall be reported to the Manager of QA/NS and the Chief Operating Officer.
'16. Review of.the security plan and recommended changes shall be submitted to the "D.irac_tpI_q1._. Corporate Security and_the AVP OuAllty EIQ9IAmn and_&sjianament" rather than to the " Assistant Vice President-and General Manager Nuclear Stations".
- 17. Procedures and changes thereto must be authorized by the "Etatina l
Manager" before implementation rather than by a " Station j
Superintendent".
1 The applicable Unit Two Technical Specifications Section 6 pages have been retyped and the following grammatical and typographical errors are being corrected at this time.
1.
Section 6.1.C "a" to "at" 2.
Section 6.1.G.1.a.
i "shall" to "shalls"
" posses" to " possess"
" function" to " function,"
3.
Section 6.1.G.1.b.(8)
"of" to "the" "Least" to "least" 4.
Section 6.1.G.2.a.
Y
" directions," to " directions;"
" posses" to " possess" 5.
Section 6.1.G.2.b.
" area" to " areas" 6.
Section 6.1.G.2.e.
I
" Manager shall" to " Manager, shall" l
l l
1516B 1
i
, s ATTACIRIDD'_C l
EALUAIl0tLOLSEH1flCANJ_.UAIARD CONS 3DIRAT10ES i
Commonwealth Edison has evaluated this proposed snendment and determined that it involves no significant hazards consideration.
According to 10 CFR 50.92(c), a proposed amendment to an operating 11 cense involves no j
significant hazards considerations if operation of the facility in accordance with the proposed snendment would not:
1.
Involve a significant increase in the probability or consequences of an accident previously evaluated; or 2.
Create the possibility of a new or different kind of accident from any accident previously evaluated; or 3.
Involve a significant reduction in a margin of safety.
The proposed Technical Specification amendment requests several changes. The first change involves the removal of organizational Figures 6.1-1 and 6.1-2 and the revision of TS 6.1.A, 6.1.B, and 6.1.C in accordance wit.h the guidance provided in Generic Letter 88-06.
The second proposed revision corrects several position titles that changed due to corporate reorganization. The third change clarifles the distribution requirements for onsite review documentation discussed in TS 6.2.
The fourth change involves a i
i position change from Radiation Chemistry Technician to Radiation Protection and Chemistry Technicians in specification 6.1.D.
The fifth and last changes are typographical corrections or editorial in nature.
None of the proposed changes are initiating events for an accident, therefore, the probability of an occurrence of an accident is not affected.
Even though the organizational figures are being removed, TS 6.1.A is being revised to require the organizational figures, functional descriptions of departmental responsibilities and relationships and job descriptions for key personnel positions be maintained for the Quality Assurance manual or the Management Plan for Operations, Sections 3 and 6.
Therefore, safe plant operation is not affected and the consequence of any accidents presented in the UFSAR are not imparted by the first change. The remaining changes address organizational changes, and clarification for documentation distribution, editorial and typographical changes.
All these changes are administrative in nature and the consequences of an accident as described in the UFSAR are not affected.
/scl:5428K 36 l
1
1 l
The proposed changes do not revise any functional or design parameters used at the Station. These changes do not modify any equipment or systems or cause the unit to be operated in a dif ferent manner. Therefore, the possibility of.a new or different kind of accident is not created.
All the proposed changes are administrative, editorial or typographical and, as such, do not affect any margins of safety. The proposed organization changes do not affect safe operation of the plant.
Creation of a Radiation Protection Technical position in lieu of a Radiation Chemistry Technician adequately meets the requirements for Health Physics coverage identified in NUREG 0123.
Updating position titles, clarifying documentation distribution requitcments, editorial and typographical changes, facilitate plant operations but do not affect safe operations.
For the preceding reasons, Commonwealth Edison believes all the changes proposed for the Technical Specification snendment do not involve any significant hazards considerations.
i l
/sc1:5428K 35 l
1
AHACIMEtiT_D SAFETY EVALUATION AND ENVIRONMENTAL ASSESSMENT
~
Typically onsite and offsite organizations are defined by organization charts included under administrative control requirements of the Technical Specification (TS).
This requires the processing of a license amendment to change an organization chart before implementing a change in 1
(
organizational structure. The guidance provided in Generic Letter 88-06 addresses amendments that may be proposed for removing organization charts from the a&ninistrative control requirements of the TS.
1 l
The staff has previously determined that with appropriate changes to l
these administrative control requirements, the onsite and offsite organization l
charts may be removed.
The changes involve the addition of general l
requirements that capture the essential aspects of the organizational l
structure that are defined by existing onsite and offsite organization charts. to Generic Letter 88-06 provides guidance for license amendment requests to remove organization charts from TS.
l to Generic Letter 88-06 provides an example of this change that was made to the administrative control requirements of the existing Westinghouse Standard Technical Specifications (STS). The staff has i
found that this change will not reduce plant safety and it is generically applicable to all power reactors.
The removal of organization charts is a line item improvement that was proposed on a lead-plant basis for the Shearon Harris plant and was endorsed by the Westinghouse Owners Group.
This change was reviewed as part of the NRC's program for improvements in TS.
The objectives of that program were estal11shed by the Commission's Interim Policy Statement on Technical Specification Improvements. The staff concludes that the removal of organization charts from TS will provide greater flexibility for licenses to implement changes in both the onsite and offsite organizational structure, consistent with Commission policy.
Commonwealth Edison has evaluated the proposed snendment against the criteria for and identification of licensing and regulatory actions requiring environment assessment in accordance with 10 CFR 51.21.
It has been determined that the proposed changes meet the criteria for a categorical exclusion as provided for under 10 CFR 1.22(c)(9).
This determination was based on the fact that changes are being proposed as an snendment to a license issued pursuant to 10 CFR 50.
The changes are of an administrative nature only.
The changes involve no significant hazards, there are no significant changes in the types or amounts of off-site effluents, and there are no signifi cant increases in individual or cumulative occupational exposure.
/sc1:5428K:9 I
i