ML20093N518
| ML20093N518 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 07/25/1984 |
| From: | FLORIDA POWER CORP. |
| To: | |
| Shared Package | |
| ML20093N511 | List: |
| References | |
| NUDOCS 8408020018 | |
| Download: ML20093N518 (18) | |
Text
. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
_T Table 3,7-3 3
SAFETY RELATED MYDRAUllt SNUG 8ER$*
5 P
SNUOWER SYSTEM $ NUB 9ER INSTALLEO ON, ACCES$19tE 04 W1CN RADIATION ESPECIALLY DInfCULT q
NO.
LOCATION ** AND ELEVATION __ JNACCESSISLE_
20NE****
TO ROEITE
[K or il ITes or Nel (Tes or Nel p
Decay Meat Removal System U
DNN-17 R8 110'-6" I
No We DHH-18 R8 110'-6" I
No No l
DHH-19 R8 109'-0" I
No No i
i DHH-20 R82 115'-0" I
Yes No DHH-21 R82 117'-0" I
Yes Yes 1
DHH-22 RB2 117'-0" I
Yes Yes 1
DHH-23 RB 110'-6" 1
No Yes j
DHH-24 PS 109'-3" I
No No j
3 DHH-25 R8 110'-6" I
No Yes w
DHH 26N RS 110'-6" No No 4
DHH-26Y R8 110'-6".
I No No u
DHH-27 R8 110'-6" I
- No Yes i
DHH-35 R82 152'-5" I
Yes No DHH-36 RB2 152'-5" 1
Yes No DHH-37 RB2 159'-7" l
Yes Yes DHH-38 R82 160'-1" I
Yes Yes DHH-39 RB2 165'-9" I
Yes No i
DHH-661 A8 86'-6" A
Yes No
)
A Yes No i
DHR-18 A8 84'-7" j
DHR-21 AB 103'-6" A
No No DHR-24U AB 129'-6*
A No No DHR-24L A8 129'-6" A
No No DHk-28 AB 134'-4" A
No No DHR-31 A8 84'-9" A
Yes No DHR-31 A8 85'-6" A
Yes No A
Yes No DHR-49 A8 85'-6" 8408020018 840725 PDR ADOCK 05000302 P
PDR l
t
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Table 3.7-3 SAFETY KLAftB _NTORAULIC $NU90ER$*_
f 5
$NUO9ER SYSTEM SNUsett INSTALLED ACCESSIR E OR NIGN RARIATION ESPECfELY DIFFICULT M
l q
NO.
C1, LOCATION" AND ELEVATION INACCESSIBLE ZONE" *
- _TO REf0VE TE~or II (Yes or Nel IYes or Not i
h Emergency Feedwater System U
EFM-14U R9 115'-O" I
No No W
EFM-14L R8 115'-0" I
No No 1
EFN-15U R8 115'-0" I
No No i
I EFN-15L R8 115'-0" I
No No i
EFN-27 R82 145'-9" I
Yes Yes t
)
EFM-28 R82 145'-9" Yes Yes
[FM-92 18 140'-0" I
No No
[FN-93 18 131'-8" I
No N1
)
EFN-94 18 131*-8" A
No N3 EFN-95 18 1c0'-0" A
'No No 4,
EFH-96 18 141'-3" A
No No y
I No hs EFH-106 18 141'-3*
I LFH-107 18 141'-3" A
No No EFH-108 18 141'-3" A
No Ie EFM-109 18 133'-0*
A No he j
[FM-110 18 133'-0" I
No We l
j
[FM-141 18 126'-6*
A No I:o j
[FH-143 18 133'-6" A
No So l
EFN-144 18 141'-3" I
No llo I
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CRYSTAL RIVER - WIT 3 3/4 7-31 t
Table 3.7-3 n*
SAFETY RELATED HYDRAULIC SNUBBERS
NO.
LOCATION ** AND ELEVATION INACCESSIBLE ZONE ****
TO REMOVE j
(A orI)
(Yes or No)
(Yes or No) z 3
E Post Accident Venting System 7
w LRH-59 AB 160'- 10" A
No No LRH-60 AB 160'- 10" A
No No LRH-63 AB 161'- 0" A
No No LRH-69 AB 161'- 0" A
No No 5
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CRYSTAL RIVER - WIT 3 3/4 7-33
Table 3.7-3
- c g
SAFETY RELATED HYDRAULIC SNUBBERS
- 9 h
SNUBBER SYSTEM SNUBBER INSTALLED ON, ACCESSIBLE OR HIGH RADIATION ESPECIALLY DIFFICULT q
NO.
LOCATION ** AND ELEVATION INACCESSIBLE ZONE ****
TO REMOVE g
(A orI)
(Yes or No)
(Yes or No)
Cz Reactor Coo; ant System (Cont'd) w RCH-67 RB2 166'- 0" I
Yes No RCH-68 RB2 167'- 1" I
Yes No RCH-69 RB2 167-1" I
Yes No RCH-70 RB2 167'- 1" I
Yes No R
RCH-71U RB2 167'- 1" I
Yes No
[
RCH-71L RB2 167'- 1" I
Yes No a,
RCH-73 RB2 167'- 1" I
Yes No RCH-74 RB2 167'- 1" I
Yes No RCH-76 RB2 139'- 11" I
Yes Yes RCH-77 RB2 131'- 6" I
Yes Yes RCH-78 RB2 150'- 10" I
Yes Yes RCH-79 RB2 156'- 8" I
Yes Yes RCH-80 RB2 168'- 3" I
Yes No RCH-81 RB2 168'- 4" I
Yes No RCH-82E RB 143'- 9" I
No Yes RCH-82W RB 143'- 9" I
No Yes RCH-83 RB 145'- 11" I
No No RCH-84 RB 123'- 9" I
No No RCH-85 RB 147'- 0" I
No No j
RCH-86 RB 144' 9"
I No No RCH-87 RB 147'- 0" I
No No RCH-88 RB 147'- 0" I
No No i
RCH-89 RB 124'- 0" I
No No l
RCH-90 RB 120'- 0" I
No No RCH-530 RB2 170'- 6" I
Yes No RCH-531 RB2 170'- 6" I
Yes No 4
i
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President l
Executive t
y Vice President
-4 w
i i
Nuclear General Review Comm.
Vice President l
Engineering Services l
Sensor I
Vice President I
'Vice President Administrative Director Nuclear Services Environmental &
Operations Licensing Manager Affairs Nuclear Support Services I
I I
C5 Director Director Director
- Director Director b
Purchasing &
Quality Nuclear Operations Site Nuclear Nuclear Operations Stores Programs Engineering &
Operations Materials &
Licensinz Controls I
I I
I I
Director Manager Nuclear Nuclear Plant Nuclear Outage Nuclear Operations Nuclear Operations Assistant Fuel &
Power Plant Compliance
- Manager
& Modifscations Training Admir.istratave to Director Special Materials Manager Manager Manager Manager Site Nuclear Projects prations l
The Corporate Organization may be changed without prior License Amendment to Figure 6.2 -1 provided that a revision to Figure 6.2 -1 is included with the nest License Amendment request.
FIGURE 6.21
- Indacates position having fire protection responsibility.
CORPOR ATE ORGANIZATION l
i l
- Nuclear Plant Manager 1
I
- Nuclear Plant
- Nuclear Plant Operations Engineering and Technical Services o Operations Staff:
o Inservice
- Shif t Supervisor (SOL)
Inspection
- Licensed Operators (OL)
- Non Licensed Operators o Reliability & Performance Reviews o Fire Protection o Maintenance:
o Technical
- Electrical Specification
- Mechanical Coordination
- Instrumentation &
Control o Reactor Physics
- Building Servlees o Compliance Reviews o Health o Nuclear Security Physics o Chemical o Safety Reviews Control o Plant Engineering:
o Waste
- Electrical a
Management
- Mechanical
- Instrumentation & Control o Compliance Reviews
- Structural
- Computer Lcgend: SOL - Senior Operator License OL - Operator License
- - Fire Protection Responsibilities The Facility Organizatib may be changed without prior License Amendment to Figure 6:2.2 provided that a revision to Figure 6.2.2 is included with the next License Amendment request.
Figure 6.2-2 FACILITY ORGANIZATION 6-3
ADMINISTRATIVE CONTROLS 6.3 FACILITY STAFF QUALIFICATIONS 6.3.1 Each member of the facility staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions, except for the l
Chemistry and Radiation Protection Superintendent who shall meet or exceed l
the qualifications of Regulatory Guide 1.8, September 1975, and the Operations Technical Advisor, who shall have a Bachelor's degree, or the equivalent, in a scientific or engineering discipline with specific training in plant design and response and analysis of the plant for transients and accidents.
6.4 TRAINING
'6.4.1 A retraining and replacement training program for the facility staff shall be maintained under the direction of the Director, Site Nuclear Operations and shall l
meet or exceed the requirements and recommendations of Section 5.5 of ANSI N18.1-1971 and Appendix "A" of 10 CFR Part 55.
6.4.2 A training program for the Fire Brigade shall be maintained under the direction of the Director, Site Nuclear Operations and shall meet or exceed the l
requirements of Section 27 of the NFPA Code-1976, except for Fire Brigade training sessions which shall be held at least quarterly.
6.5 REVIEW AND AUDIT 6.5.1 PLANT REVIEW COMMITTEE (PRC)
FUNCTION 6.5.1.1 The Plant Review Comrnittee shall function to advise the Nuclear Plant Manager on all matters related to nuclear safety.
COMPOSITION
-6.5.1.2 The Plant Review Committee shall be composed of the:
Chairman: Nuclear Operations Superintendent Member:
Assistant Nuclear Plant Engineer & Technical Services Manager Member:
Nuclear Maintenance Superintendent Member:
Nuclear Security and Special Projects Superintendent Member:
Nuclear Compliance Supervisor Member:
Nuclear Chem / Rad Protection Superintendent Member:
Nuclear Plant Engineering Superintendent Member:
Nuclear Safety & Reliability Superintendent Member:
At Large (Designated by Chairman)
Member:
At Large (Designated by Chairman)
ALTERNATES 6.5.1.3 All alternate members shall be appointed in writing by the PRC Chairman to serve on a temporary basisl no more than two alternates shall participate as voting members in PRC activities at any one time.
MEETING FREQUENCY 6.5.1.4 The PRC shall meet at least once per calendar month and as convened by the PRC Chairman or his designated alternate.
CRYSTAL RIVER - UNIT 3 6-5 a
ADMINISTRATIVE CONTROLS QUORUM 6.5.1.5 A quorum of the PRC shall consist of the Chairman or his designated alternate and five members including alternates.
RESPONSIBILITIES 6.5.1.6 The Plant Review Committee shall be responsible fort a.
Review of 1) all procedures and changes thereto as required by Specification 6.8.2, 2) any other proposed procedures or changes thereto as determined by the Nuclear Plant Manager to affect nuclear safety.
b.
Review of all proposed tests and experiments that affect nuclear safety.
c.
Review of all proposed changes to the Appendix "A"
Technical Specifications.
d.
Review of all proposed changes or inodifications to plant systems or equipment that affect nt. clear safety, and changes to Radwaste Systems which could significantly alter their ability to meet Appendix 1.
Investigation of all violations of the Technical Specifications including the e.
review of reports covering evaluation and recommendations to prevent l
recurrence to the Vice President, Nuclear Operations and to the Chairman of the Nuclear General Review Committee.
f.
Review of events requiring 24-hour written notification to the Commission.
g.
Review of facility operations to detect potential nuclear safety hazards.
h.
Performance of special reviews, investigations or analyses and reports thereon as requested by the Chairman of the Nuclear General Review Committee.
1.
Review of the Plant Security Plan and implementing procedures.
J.
Review of the Emergency Plan and implementing procedures.
CRYSTAL RIVER - UNIT 3 6-6
ADMINISTRATIVE CONTROL 5 COMPOSITION 6.5.2.2 The NGRC shall be composed of the Chairman, Vice Chairman, and at least 5 members. No more than a minority of the members shall have line responsibility for operation of the facility.
The committee shall collectively have the experience and competence required to review problems in the following areas:
a.
Nuclear power plant operations b.
Nuclear engineering c.
Chemistry and radiochemistry d.
Metallurgy e.
Nondestructive testing f.
Instrumentation and control g.
Radiological safety h.
Mechanical and electrical engineering 1.
Administrative controls J.
Environmental k.
Quality assurance practices QUALIFICATIONS 6.5.2.3 The following minimum experience requirements shall be established for tHose persons involved in the independent off-site safety review and audit programs:
a.
Chairman and Vice Chairman-Bachelor of Science in engineering or related field or the equivalent and ten years related experience including five l years involvement with operation and/or design of nuclear power plants, b.
Member-Bachelor of Science in engineering or related field or the equivalent and five years related experience including three years involvement with operation and/or design of nuclea power plants.
ALTERNATES 6.5.2.4 All alternate members shall be appointed in writing by the NGRC Chairman to serve on a temporary basisl however, no more than two alternates shall participate as voting members in NGRC activities at any one time.
CRYSTAL RIVER - UNIT 3 6-8
CONSULIMIS l
6.5.2.5 Consultants shall be utilized as determined by the NGRC Chairman to provide expert advice to the NGRC.
IdEEIlNG PREQUENCY 6.5.2.6 The NGRC shall meet at least once per calendar quarter during the initial year i
of facility operation following fuel loading and at least once per six months thereafter.
M 6.5.2.7 A quorum of NGRC shall consist of the Chairman or his designated alternate and five additional NGRC members, including alternates. No more than a minority of the quorum shall have line responsibility for operation of the facility.
REVIEW 6.5.2.8 The NGRC shall reviews a.
Safety evaluations of changes to the facility, changes in procedures and tests and experiments not described in the Final Safety Analysis Report which were completed without prior NRC approval.
b.
Proposed changes in the facility, changes in procedure or proposed tests or i
experiments which may involve an unreviewed safety question.
c.
Proposed changes in the Technical Specifications or license amendments relating to nuclear safety prior to implementation, except in those cases where the change is identical to a previously reviewed proposed change.
i d.
Violations, deviations and reportable events, which require reporting to the Nuclear Regulatory Commission in writing within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. This review should include results of investigations and recommendations resulting from such investigations.
e.
Any other matter involving safe operation of the plant which an independent reviewer deems appropriate for consideration, or which is l
referred to the reviewers by members of Nuclear Operations staff or by other functional organizational units within Florida Power Corporation.
{
f.
Reports and meeting minutes of the Plant Review Committee.
g.
Changes to the " Process Control Program" and to the Offsite Dose Calculation Manual.
1 4
. CRYSTA. l, RIVER UNIT. 3___ _.__ _6-9_
e g.CJNTROL5 AUDITS 6.5.2.9 Audits of facility 6:tivities shall be performed under the cognizance of the NGRC. These audits shall encompass a.
The conformance of facility operation to provisions contained within the Technical Specifications and applicable license conditions at least once per 12 months.
b.
The performance, tralair g and qualifications of the entire facility staff at least once per 12 n'ootha.
c.
The results of ac*lx.s taken to correct deficiencies occurring in facility equipment, structures, systems or method of operation that affect nuclear safety at least once par 6 months.
d.
The performance of activities required by the Operational Quality Assurance Progr,sm to meet the criteria of Appendix "B",10 CFR 50, at least once per 24 'nonths.
The Facility Emergency Plan acd implementing procedures at least once e.
per 12 months, f.
The Facility Security Plan and implementing procedures at least once per 12 months.
g.
The Facility Fire Protection Program and implementing procedures at least once per 12 months.
h.
The Radiological Envi onrnental Monitoring Program and the results thereof at.' east once per 12 inonths.
- i.
The Offsite Da>e Calculation f.tanual and implementing procedures at least once per ?4 months.
J.
Tin Process Contral Program and implementing procedures for
.tolliificatloa of radmdive wastes at least once per 24 months.
k.
The performance of activities reouired by the Quality Assurance Program for eifluent and environmental mon!toring at least once per 12 months.
'l.
Any other area el facility operation considered appropriate by the NGRC or the Executive Vice Presider.t.
MHORITY 6,? 1.10 The NGRC sf.all report to and advise the Executive Vice President on those areas pf renpensibility specified in Sections 6.5.2.8 and 6.5.2.9.
I b
4 CRYSTAL RIVER - UNIT 3 6-10
4 M-__-._..___-____-.
4 ARE121U21 6.5.2.11 Records of NGRC activities shall be prepared, approved and distributed as indicated belows Minutes of each NGRC meeting shall be prepared, approved and forwarded I
a.
to the Executive Vice President within 14 days following each meeting.
l Reports of reviews encompassed by Section 6.5.2.8 above, shall be b.
prepared, approved and forwarded to the Executive Vice President within 14 days following completion of the review.
Audit reports encompassed by Section 6.5.2.9 above, shall be forwarded to c.
[
the Executive Vice President and to the management positions responsible for the areas audited within 30 days af ter completion of the audit.
6.6 REPORTABLE OCCURRENCE ACTION 6.6.1 The following actions shall be taken for REPORTAB1.E OCCURRENCES:
The Commission shall be notified and/or a report submitted pursuant to the a.
requirements of Specification 6.9.
Each REPORTABLE OCCURRENCE requiring 24-hour notification to the b.
Commission shall be reviewed by the PRC and submitted to the NGRC and the Vice President, Nuclear operations.
i 4
l CRYSTAL P.IVER - UNIT 3 6 11 L
t f
____.._.,.m_._-,__,-y,
.-.r.
ADMINISTRATIVE CONTROLS 6.7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a Safety Limit is violated:
The facility shall be placed in at least HOT STANDBY within one hour.
a.
b.
The Safety Limit violation shall be reported to the Commission, the Vice President, Nuclear Operations and to the NGRC within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
A Safety Limit Violation Report shall be prepared. The report shall be c.
reviewed by the PRC.
This report shall describe (1) applicable circumstancea preceding the violation, (2) effects of the violation upon facility components, systems or structures and (3) corrective action taken to prevent recurrence.
d..
The Safety Limit Violation Report shall be submitted to the Commission, the NGRC and the Vice President, Nuclear Operations within 14 days of the violation.
6.8 PROCEDURES 6.8.1 SCOPE Written procedures shall be established, implemented and maintained covering the activities referenced below:
s x
. The applicable procedures. recommended in Appendix "A" of Regulatory a.
Guide 1.33, November,1972.
b.
Refueling operations.
- c.. Surveillance and test acti9ities of safety related equipment.
d.
Security Plan implementation.
Emergency Plan impie' mentation.
c.
f.
Fire Protection Program implementation.
g.
Systems Integrity Program implementation.
h.
lodine Monitoring Program implementation.
i.
PROCESS CONTROL PROGRAM implementation.
J.
OFF-SITE DOSE CALCULATION' MANUAL implementation.
k.
Quality Assurance Prograh for effluent and environmental monitoring.
l 6.8.2 REVIEW PROCESS
/
6.8.2.1 Each prec$ dure and administrative policy of 6.8.1 above, and changes thereto, shall be reviewed and apprc,ved prior to implementation as follows:
The Emergency Plan, Security Plan, Fire Protection Plan and implementing
- a.
procedurcis, Administrative Instructions, and those test procedures associated with safety related plant modifications shall be reviewed by the PRC and approved by the Nuclear Piant Manager prior to implementation.
a CRYSTAL RIVER - UNIT 3 12 t
s.
J - -
ADMD457RATIVE CONTROLS b.
For all other procedures, the review cycle shall consist of: an intradepartmental review by a Qualified Reviewer, an interdisciplinary
(
review by Qualified Reviewer (s) in interfacing departments, as specified in Administrative Procedures, and approval by the responsible Superintendent or Manager, as specified by Administrative Procedures. The PRC shall then review the 10 CFR 50.59 evaluation within 14 days of approval.
6.8.2.2 The training and qualification of Qualified Reviewers shall be governed by l
Administrative Procedures, with final certification by the Nuclear Plant Manager. Recertification will be required on a periodic basis and upon transfer between departments. As a minimum, all Qualified Reviewers shall meet the requirements of ANSI N18.1-1971, Sections 4.2, 4.3, 4.4, or 4.6, or the equivalent.
6.8.2.3 Each procedure and administrative policy of 6.8.1 shall be reviewed on a periodic l
basis as set forth in Administrative Procedures.
I CRYSTAL RIVER - UNIT 3 6-12a
4 ADMINISTRATIVE CONTROLS
(
MONTHLY OPERATING REPORT 6.9.1.6 Routine reports of operating statistics and shutdown experience shall be submitted on a monthly basis to the Director, Office of Inspection and Enforcement, U.S.
Nuclear Regulatory Commission, Washington, D.C.
- 20555, with a copy to the Regional Office, no later than the 15th of each month following the calendar month covered by the report.
REPORTABLE OCCURRENCES 6.9.1.7 The REPORTABLE OCCURRENCES of Specifications 6.9.1.8 and 6.9.1.9 below, including corrective actions and measures to prevent recurrence, shall be reported to the NRC. Supplemental reports may be required to fully describe final resolution of occurrence. In case of corrected or supplemental reports, a licensee event report shall be completed and reference shall be made to the original report date.
PROMPT NOTIFICATION WITH WRITTEN FOLLOW-UP 6.9.1.8 The types of events listed below shall be reported within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by telephone and confirmed by telegraph, mallgram, or facsimile transmission to the Director of the Regional Office, or his designate, no later than the first working day following the event, with a written follow-up report within 14 days. The written follow-up report shall include, as a minimum, a completed copy of a licensee event report form. Information provided on the licensee event report form shall be supplemented, as needed, by additional narrative material to provide complete explanation of the circumstances surrounding the event.
a.
Failure of the reactor protection system or other systems subject to limiting safety-system settings to initiate the required protective function by the time a monitored parameter reaches the setpoint specified as the limiting safety-system setting in the technical specifications or failure to complete the required protective function.
b.
Operation of the unit or affected systems when any parameter or operation subject to a limiting condition for operation is less conservative than the least conservative aspect of the limiting condition for operation established in the techical specifications.
c.
Abnormal degradation discovered in fuel cladding, reactor coolant pressure boundary, or primary containment.
CRYSTAL RIVER - UNIT 3 6-15