ML17325A477
| ML17325A477 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 11/17/1987 |
| From: | Wigginton D Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8712010263 | |
| Download: ML17325A477 (21) | |
Text
ll November 17, 1987 Docket Nos.
50-315 and 50-316 LICENSEE: Indiana and Michigan Power Company FACILITY: Donald C.
Cook Nuclear Plant, Unit Nos. I and 2
DISTRIBUTION:
NRC 8 Local PDRs PDIII-3 r/f DWigginton OGC-Bethesda EJordan JPar tlow ACRS(10)
SUBJECT:
SUMMARY
OF MEETING HELD ON NOVEMBER 9, 1987 TO DISCUSS DIESEL GENERATOR OIL TESTING AND ON-SITE SAFETY REVIEW COMMITTEE The staff met with the licensee on November 9, 1987 in Bethesda to discuss the proposed program to test and clean the diesel generator oil tanks.
The licensee also presented their proposed technical specifications for changes to the on-site safety review committee.
The list of attendees is attached as Enclosure 1.
The two diesel generator oil tanks at Cook are aligned to each provide fuel to a diesel generator in each unit.
To empty a tank for cleaning would cause each unit to have to shutdown because each unit would have an inoperable diesel generator for a period which exceeds the technical specification limit.
Cook proposes to clean the tanks by mixing or agitating the fuel and filtering the agitated fuel to below impurity levels.
Cook agreed to design the system and propose acceptance criteria for impurities based on a clean tank examination for NRR review before the system was put into use.
This review should not hold up the issuance of the remaining technical specifi-cations.
The licensee also agreed to perform an accumulated water test every 31 days by use of a tape or putty compound; the exact method will be proposed for the Basis section of the Technical Specifications.'he indicator will be lowered through the fill line to the lowest point in the tank.
This is
'acceptable to determine accumulated water below the fuel oil; the fuel lines to the diesels are located at the other and higher end of the tank.
The accumulated water would be removed from the low end by suction.
The definition of "all" accumulated water will be proposed for the Basis section also.
Cook is expected to submit their technical specifications with the above changes in 2 to 3 weeks.
The submittal will also propose when the technical specifications are to go into effect.
ev>~o~0~~
q0OQSiS vxii/
PgR ADOCK 0
@0'
v 4 ll r
ld I( l 4 I(
I
v Nr J '4 II
) 14 4
j 4
/
~
4 4+
4 I dt dr Ir gt 1
N rl
('I 4
E I
~ 4 tr(Ey I, j'
I IEEv
'd v
November 17, 1987 I The licensee also discussed proposed technical specifications to address the Plant Nuclear Safety Review Coenittee (PNSRC).
The technical specifications discussed are in Enclosure 2.
Several suggestions were made to update require-ments to current acceptable language.
Cook will consider the suggestions and formally submit the technical specifications to the NRR.
Enclosures:
As stated lo/
David L. Wigginton, Project Yianager Project Directorate III-3 Division of Reactor Projects cc:
See next Page Office:
LA/P I Surname:
PKreu er Date:
11/ f7/87 PD/PDIII-3 DWigginton 11( 7 /87
I N V I,*
v t
I
Mr..John Dolan Indiana and Michigan Electric Company Donald C.
Cook Nuclear Plant CC:
Mr. M. P. Alexich Vice President Nuclear Operations American Electric Power Service Corporation 1 Riverside Plaza
- Columbus, Ohio 43215 Attorney Gener al Department of Attorney General 525 West Ottawa Street Lansing, Michigan 48913 Township Supervisor Lake Township Hall Post Office Box 818 Bridgeman, Michigan 49106 W. G. Smith, Jr., Plant Manager Donald C.
Cook Nuclear Plant Post Office Box 458 Bridgman, Michigan 49106 U.S. Nuclear Regulatory Commission Resident Inspectors Office 7700 Red Arrow Highway Stevensville, Michigan 49127 Gerald Charnoff, Esquire Shaw, Pittman, Potts and Trowbridge 2300 N Street, N.W.
Washington, DC 20037 Mayor, City of Bridgeman Post Office Box 366 Bridgeman, Michigan 49106 Special Assistant to the Governor Room 1 - State Capitol Lansing, Michigan 48909 Nuclear Facilities and Environmental Monitoring Section Office Division of Radiological Health Department of Public Health 3500 N. Logan Street Post Office Box 30035 Lansing, Michigan 48909 Regional Administrator, Region III U.S. Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, Illinois 60137 Mr. J. Feinstein American Electric Power Service Corporation 1 Riverside Plaza
- Columbus, Ohio 43216
ENCLOSURE 1
bfAME D. Wigginton David Shum Robert Giardina Gregory D. Hines Clair Nanges B. A. Svensson P. A. Barrett T. A. Kriesel M. G. Smith, Jr.
Fred Allenspach DIESEL GENERATOR TECH SPEC MEETING D. C.
COOK NOVEMBER 9, 1987 ORGANIZATION PDIII-3 PSB OTSB AEPSC AEPSC Cook Plant AEPSC DC Cook DC Cook PEB
ENCLOSURE 2
MR~ISHRTIVE CONi ROLS
- 6. 1 RESPONSIBILITY 6.1.1 The Plant Manager shall be responsible for overall facility operation and shall delegate in writing the succession to this responsibility during his absence.
- 6. 2 ORGANIZATION OFFSITE 6.2.1 The offsite organization for facility management and technical support shall be as shown in Figure 6.2-1.
FACILITYSVFF 6.2.2 The facility organizatian shall be as shown on Figure 6.2-2 and:
a.
Each on duty shift shall be canposed of at least the minimum shift crew ocxnposition shown in Table 6.2-1.
b.
At least one licensed Operator shall be in the control nxxn when fuel is in the reactor.
c d.
At least twa licensed Operators shall be present, in the control rmxn during reactor start up, scheduled reactor shutdown and during recovery fran reactor trips.
An individual qualified in radiation protection procedures shall be on site when fuel is in the reactor.
e.
All CORE ALTERATIONS shall be directly supervised by a Seniar Reactor Operator, further qualified in Fuel Handling, who has no other cancurrent responsibilities during this operation.
A site Fire Brigade of at least 5 embers shall be maintained ansite at all times.
The Fire Brigade shall not include 3 members of the minimum shift crew necessaxy for safe shutdown of the unit or any personnel required for other essential functions during a fire emergency g.
The armunt of overtire worked by plant staff me@hers performing safety-related functions must be limited in accordance with NRC Policy Statement on working hours (Generic Letter No. 82-12).
The individual qualified in radiatian protectian pxxeedures and the cxxngosition of the Fire Brigade may be less than the minimum requiranents for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, in order to accaanodate unexpected absence pravided imrediate action is taJmn to fillthe required positions.
D. C.
OOQK UNIT 2 6-1 Amendment No.
12/PBmn
7t gal'5c Rem>rl'5sw~ca sgg~gv/ddt
~
~
~
~
~ ~
~
~
~
~
~
~
~
ADHINISTRATIVE RESPONSIBILITY
--, f UNCTIONAL RESPONSIBILITY
'""" TECHNICAL LIAlSON aaaner
~
RAIT IMARI
%SCTQI AtCZTNfT IlJÃf IWNKR WSNE1ATXS ~
~TER nsocw.
SFCK~Xt QfCTT OO ARKRSEXf gdd. S+
~
Orei f; vs al
+dl HCIL/cs g~ggls04 guC<CWK'd.Wiui4C S Pg
~NILifY sdC 4<%
hxiPlC6'4 Sacg goy Cd+) 4d+
tlg4AC4 4 J(cggr4 s/ill sr'
~~)/q s'cw LEGEND:
SOL Senior Onerator License
~ - Key Supervisory Figure 6.2-2 Personnel Facility Organization - Donald C.,Cook Unit No.
2 iY The llealth Physics Supervisor has direct access to the Plant Manager in matters concerning any phase of radiological protection.
O'ntil a Health Physics Supervisor, with qualifications meeting the criteria specified in Regulatory Guide 1.8, September 1975, is designated, the Technical Physical Science Superintendent will fulfillthis responsibility.
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 ccmparable positions, except for (1) the Plant Health Physics Supervisor, who shall meet or exceed the qualifications of Regulatory Guide 1.8, September
- 1975, and (2) the Shift Technical Advisor, who shall have a 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.
6.4 TRAINING 6.4.1 A retraining and replacement training program for the facility staff shall be maintained under the direction of the Training Manager and shall meet or exceed the requirements and reccamendations 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 Plant Manager and shall meet or exceed the requirements of Section 27 of the NFPA Code-1976.
6.4.3 Only the individual(s) assigned the responsibility of fulfilling Technical Specification 6.2.2.e are required to maintain training cccrmensurate with their Fuel Handling responsibilities.
6.5 REVIEW AND AUDIT 6.5.1 PLY NUCLrea SAFZZY REVE% CrNNrTrEZ (PNSRC)
H3NCTION 6.5.1.1 The PNSRC shall function to advise the Plant Manager on all matters related to nuclear safety.
CXMPOSITION 6.5.1.2 The PNSRC shall be cxmposed of the:
ChalZIABI1 Metrber.
Member:
Marber:
Marher.
Menher:
Member:
Assistant, Plant Manager Organization
& Adtninistration or Designee Licensing Activities Coordinator Assistant Plant Manager Technical Support Operations Superintendent Technical Engineering Superintendent Technical Physical Sciences Superintendent Maintenance Superintendent D.C.
COOK UNIT 2 3/PEEK'rT 6-5 Amendment No.
ALTERNATES 6.5.1.3 All alternate rrembers shall be appointed in writing by the PNSRC Chairnan to serve on a temporary basis; however, no more than two alternates shall participate as voting members in PNSRC activities at any one timo.
6.5.1.4 The PNSRC shall meet at least once per calendar month and as convened by the PNSRC Chairman or his designee.
6.5.1.5 A quorum of the PNSRC shall consist of the Chairman or his designee and sufficient members, of which no more than two shall be alternates, to constitute a majority.
RESPONSIBILITY 6.5.1.6 The PORC shall be responsible for:
a.
Review of all Plant Manager Instructions (XBXs) and revisions thereto.
The review of PMXs and revisions thereto may occur at a regularly scheduled PNSRC meeting which may be after the effective date of the EKE or revision.
b.
Review of safety evaluations foi (1) plant site procedures and revisions thereto which affect the nuclear safety of the plant; (2) changes or modifications to nuclear safety related structures, systems or carponents; and (3) tests or experiaants which affect plant nuclear safety and are not addressed in the Final Safety Analysis Report or Technical Specifications to verify that such actions did not constitute an unreviewed safety question as defined in 10 CFR 50.59.
The review of the safety evaluations may occur at a regularly scheduled PORC meeting which may be after the effective date of the document or activity.
c.
Review (prior to the effective date).of proposed procedures, revisions to procedures, and cbees to equipnent, systems or facilities which may involve an unreviewed safety question as defined in 10 CFR 50.59 or requires a change in Technical Specifications.
d.
Review (prior to the implementation date) of proposed tests or experiments which may involve an unreviewed safety question as defined in 10 CFR 50.59 or requires a chape in Technical Specifications.
e.
Review (prior to the effective date) of proposed changes to Eh'A" Technical Specifications.
D-C-OOOK - UNIT 2 4/PBARET 6-6 Amexx3nant Ho.
f.
Investigation of all violations of the Technical Specifications including the preparation and forwarding of reports covering evaluation and recamerx3ations to prevent, recurrence to the Chairman of the NSDRC.
g.
Review of all REPORTABLE EV1WZS.
h.
Review of facility operations to detect potential nuclear safety hazards
~
i.
Performance of special reviews, investigations of analyses and reports thereon as requested by the Chairman of the NSDRC.
j.
Review" of the Plant Security Plan and implementing procedures and shall suhnit recmaended changes to the Chairman of the NSDRC.
k.
Review" of the Emergency Plan and implementing procedures and shall suhnit reccmrrended changes to the Chairman of the NSDRC.
1.
Review" of every unplanned onsite release of radioactive material to the environs including the preparation and forwarding of reports covering evaluation and recaarendations to prevent mamrence to the NSDRC.
m.
Review" of ch-ages to the I?ROCFSS GAZEL HIRAM, OFFSITE DOSE CALCUIATIONMANUAL, and radwaste. treatment system.
I 6.5.1.7 The PNSRC shall:
a 0 Recxmnend to the Plant Manager written approval or disapproval of items considered under 6.5.1.6(a) through (e), (j), (k) and (m).
b.
Render determinations in writing with regard to whether or not each item considered under 6.5.1.6(b) through (e) above constitutes an unreviewed safety question.
c Provide written notification within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the NSDRC of disagreanent between the PNSRC and the Plant Manager; however, the Plant Manager shall have responsibility for resolution of such disagreements pursuant to 6.1.1 above.
These reviews may be acccmplished by a cognizant individual who sumnarizes the review and findings to the PNSRC.
The cognizant individual may or may not. be a manber of the PNSRC.
D C.
COCK UNIT 2 5/pBmr 6-7 Amendment No.
AlMINISTRATIVECONXBDLS C0MPOSITION 6.5.2.2 The NSDRC shall be catposed of the following Regular Members:
a 0 b.
c d.
e.f.
gi h.
m.
n.
Vice Chairman, Engineering wxR Construction Executive Assistant to the President, I&MECo Executive Vice President and Chief Engineer Senior Vice President, Electrical Engineering and Deputy Chief EI'pincer'ice President, Mechanical Engineering Vice President, Engineering Admdzustration Vice President, Nuclear Operations (NSDRC Chairman)
Vice President, Environmental Engineering Plant Manager, Donald C. Cook Nuclear Plant Design Division Manager Manager, Quality Assurance Consulting Engineer, Nuclear Operations Division Nuclear Safety and Licensing Section Manager, Nuclear Operations Division (NSDRC Secretary)
Vice President, Fossil Plant Operations ALT1UKATE MEHK58 6.5.2.3 Designated Alternate Maribers shall be appointed by the Vice Ch-xnan, Engineering and Construction or such other person as he shall designate.
In addition, Tm~rary Altmzmte Manbers may be appointed by-the NSDRC Chaizznan to serve on an interim basis, as r~ed.
Temporary Alternate Members are em1xruered to act on the behalf of the Regular or Designated Alternate Manbers for whan they substitute.
6.5.2.4 Consultants shall be utilized as determined by the NSDRC finnan to provide expert advice to the NSDRC.
M1KTING FREQUENCY 6.5.2.5 The NSDRC shall meet at least once per six tenths.
D.C.
COGK UNIT 2 6-9 Amendment No.
6/PBME'T
6.5.2.6 A quorum, the minimum number of regular nembers and alternates required to hold a NSDRC meeting, shall be eight members, of whan no more than two shall be Designated or Temporaxy Alternates.
The Chairman or Acting Chairman shall be present, for all NSDRC meetings. If the number of members present* is greater than a quorum, then the majority participating and voting at the meeting shall not have line responsibility for operation of the facility.
For the purpose of a quorum, only the Plant Manager is considered to have line responsibility.
6.5.2.7 The NSDRC is responsible for assuring that independent** reviews of the following are performed:
a.
The safety evaluations for (1) Plant Manager Instructions and revisions thereto; (2) changes or modifications to plant nuclear safety-related structures, systems and canponents; and (3) tests or experiments which affect plant nuclear safety and are not addressed in the Final Safety Analysis Report or Technical Specifications to verify that such actions did not constitute an unreviewed safety question as defined in 10 CER 50.59.
b.
Proposed procedures, revisions to procedures, and changes to equipment or systems which involve an unreviewed safety question as defined in 10 CFR 50.59.
These reviews must be prior to the effective date.
c.
Prcposed tests or experiments which involve an uru~iewed safety question as defined in 10 CER 50.59.
These reviews must be prior to the implementation date.
d.
Proposed changes to Technical Specifications or this Operating License.
These reviews must to prior to the effective date.
e.
Violations of codes, regulations, orders, Technical Specifications, license requirements, or of internal pneedures or instructions having nuclear safety significance.
f.
Significant operating abnormalities or deviations fran normal and mcpected performance of plant equipnent that. affect nuclear safety.
g.
All REPOEKABLE EVENTS.
h.
All recognized indications of an unanticipated deficiency in sare aspect of design or operation of safety related structures,
- systems, and canponents.
i.
rts and meeting minutes of the PNSRC.
Regular NSDRC manbers are expected to attend the @meting whenever
- possible, and alternates may attend as voting manbers only on an irregular basis. Ifboth a regular menher and his alternate attend a meeting, only the regular member may participate as a voting
- member, and the alternate is considered a guest.
- Independent reviews may be performed by groups which report directly to the NSDRC and which must have NSDRC membership pm~cipation.
D.C.
COCK UNIT 2 7/Palm 6-10 Anerxhnent No.
6.5.2.8 Audits of facility activities shall be performed under the cognizance of the NSDRC.
These audits shall encanpass:
a.
'le conformance of facility operation to provisions contained within the Technical Specifications and applicable license conditions at least once per 12 months; b.
The performance, training, and qualifications of the facility staff at least once per 12 months; c.
'the results of actions taken to correct deficiencies occurring in facility equignent, structures,
- systems, or method of operation that affect nuclear safety, at least once per 6 months; d.
the performance of activities required by the Quality Assurance Pmgram to a+et the criteria of Appendix "B", 10 CFR 50, at least once per 24 months; e.
The fire protection pxogranaatic controls including the implementing procedures at least once per 24 months; f.
The fire protection equipment and pxogram implementation at least once per 12 months using either a qualified offsite licensee fire p~~on engineer or an outside independent fixe pxotection consultant.
An outside independent fire protection consultant shall be used at, least every thiLrd year; g.
We radiological Environmental Monitioring Pxogram and the results timxaf at least once per 12 months; h.
The OFFSITE DOSE CAICUZATION MANUAL and implementing procedures at least once per 24 months; The PROCESS 0M'ROGRAM and implementing procechu'es for solidification of radioactive wastes at least once per 24 months; k.
The perfoxmance of activiti.es required by the Quality Assurance Program to meet the criteria of Regulatory Guide 1.21, Rev. 1, June 1974 and Regulatoxy Guide 4.1, Rev. 1, April 1975 at least once per 12 months.
and Any crUmr area of unit operation considered appropriate by the NSDRC.
D. C.
OOOK UNIT 2 13/PBAREr 6-11 Amendment No.
6.5.2.9 The NSDRC shall report to and advise the Vice Chairman, Engineering and Construction, AEPSC, on those areas of responsibility specified in Sections 6.5.2.7 and 6.5.2.8.
6.5.2.10 Records of NSDRC activities shall be prepared, approved and distributed as indicated below:
a.
Minutes of each NSDRC meeting shall be prepared, approved and forwarded to the Vice Chairman, Engineering and Construction,
- AEPSC, within 14 days following each meeting.
b.
Reports of reviews encanpassed by Section 6.5.2.7 above, shall be prepa~R, approved and forwarded to the Vice Chairman, Engineering and Construction, AEPSC, within 14 days following canpletion of the review c.
Audit reports encxmpassed by Section 6.5.2.8 abave, shall be forwan3ed to the Vice Chaixman, Engineering and Construction, AEPSC, and to the management positions responsible for the areas audited within 30 days after cxmpletion of the audit.
D. C.
COOK UNIT 2 14/Hmm 6-12 Amendment No.
ADMINISTEQTIVE CONTROLS 6.5. 3 TfKHNICALREVIEW AhD CONTROL 6.5.3.1 Activities which affect nuclear safety shall be conducted as follies:
Procedures r~ed by Specification 6.8 and other procedures which affect plant nuclear safety, and changes thereto, shall be prepared, reviewed and approved.
Each such procedure or procedure change shall be reviewed by a qualified individual/ group other than the individual/group which prepared the procedure or procedure change, but who may be fran the same organization as the individual/group which prepared the procedure or procedure change.
Procedures other than Administrative Procedures shall be approved by the appropriate Department Head as designated in writing by the
- Manager, D. C. Cook Plant.
The Manager, D. C. Cook Plant, shall approve Mministrative Procedures, Security Plan implenanting procedures and Radiological Ihargency Response Plan implementing procedures.
Temporary changes to procedures which do not change the intent of the approved procedures shall be approved for implanentation by two mnnbers of the plant staff, at least one of whan holds a Senior Operator license, and documented.
The tangerary changes shall be approved hy the original approval authority within 14 days of implementation.
For changes to procedures which may involve a change in intent of the approved procedures, the person authorized above to approve the procedure shall approve the change prior to implementation.
b.
Proposed changes or modifications to plant nuclear safety-related structures, systems and canponents shall be reviewed as designated by the
- Manager, D. C. Cook Plant.
Each such modification shall be reviewed by a qualified individual/grc~ other than the individual/group which designed the rredification, but who may be fran the same organization as the individual/ group which designed the modifications.
Proposed modifications to plant nuclear safety-related struts, systems and carponents shall be approved prior to implementation by the Manager, D. C. Cook Plant.
c Proposed tests and experiments which affect plant nuclear safety and are not addressed in the Final Fafety Analysis Report or Technical Specifications shall be prepared,
- reviewed, and approved.
Each such test or experinent shall be reviewed by a qualified individual/group other than the individual/group which prepared the proposed test or experiment.
Proposed tests and experiments shall be approved before implementation by the Manager, D. C. Cook Plant.
d.
Individuals who approve the reviews performed in accordance with Specification 6.5.3.1a., 6.5.3.lb.,
and 6.5.3.1c., shall be mmobers of the plant management staff previously designated by the Manager, D. C. Cook Plant or the AEPSC management staff previously designated by the Vice President of Nuclear Operation.
Each such review shall include a determination of whether or not additional, cross-disciplinary review is necessary.
If deened necessary, such review shall be performed by qualified personnel of the appropriate discipline.
D.C.
QOOK UNIT 2 6-12a Amendment No.
8/PBARET
e.
Each review shall include a determination of whether or not an unreviewed safety question is involved.
Pursuant to Section 50.59, 10 CFR, NRC approval of items involving unreviewed safety questions shall be obtained prior to the Manager, D. C. Cook Plant, approval for implanentation.
f.
The Plant Security Plan and Radiological Emergency
Response
- Plan, and implarenting procedures, shall be reviewed at least once per 12 rmnths.
Recaarended changes to the implementing procedures shall be approved by the Y~ger, D. C. Cook Plant.
Reccamended changes to the Plans shall be reviewed pursuant to the requirements of Specifications 6.5.1.6 and 6.5.2.7 and approved by the Manager, D. C. Cook Plant.
hPC approval shall be obtained as appropriate.
- 6. 6 REPORZM3LE EVER ACTION 6.6.1 Each REPORM3LE EVENT requiring notification to the Conmission shall be reviewed by the PNSRC and suhnitted to the NSDRC and the Vice President, Nuclear Operations.
D.C. OXK UNIT 2 6-12b Amendment No.
9/EGRET
ADMINISTRATIVECONTROLS
- 6. 7 SAHARA LIMITVIOLATION 6.7.1 The following actions shall be taken in the event a Safety Limit is violated:
a.
The NRC Operations Center shall be notified by telephone as soon as possible and in all cases within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
'Ihe Chairman of the NSDRC shall be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
b.
A Safety Limit Violation Report shall be prepared.
the report shall be reviewed by the PNSRC.
This report shall describe (1) applicable circumstances preceding the violation; (2) effects of the violation upon facility ccmponents, systems or structures; and (3) corrective action taken to prevent recurrence.
c.
The Safety LimitViolation Report shall be nkmitted to the Gmnission, the Chairman of the NSDRC and the Vice President, Nuclear Operations within 14 days of the violation.
d.
Operation of the unit shall not be resumed until authorized by the Carmis sion.
6 8 PROC~X)UKH AND PROGRAMS 6.8.1 Written procedures shall be established, implemented, and maintained covering the activities referenced below:
a.
The applicable procedures reccmnended in Appendix "A" of Regulatory Guide 1.33, Number 1972, which affect the nuclear safety of the D. C. Cook Plant.
b.
'le Hnergency Operating Procedures required to implement the reguirerrents of NUREG-0737 and Supplement 1 to NUREX 0737 as stated in Generic Letter No. 82-33.
c.
Security Plan implementation.
d.
E nergency Plan implementation.
e.
PROCESS CONTI'ROGRAM implementation.
f.
OFFSITE DOSE CAICOZJKION MANUAL implementation.
g.
Qu-Mty Assurance Pnxp.am for effluent and environmental monitoring using the guidance in Regulatory Guide 1.21, Revisian 1, June 1974 and Regulatory Guide 4.1, Revision 1, April 1975.
6.8.2 Each procedure and adaunistrative policy of Specification 6.8.1 above, and changes thereto, including tenporary changes, shall be reviewed prior to implementation as set forth in Specification 6.5 abave.
For procedures performed by organizations in the Caqmues of the American Electric Power System (other than the D. C. Cook Facility Staff), or by contractors, the procedures and changes thereto are reviewed and appraved in accordance with an approved 10 CFR 50 Appendix "B" Qua1ity Assurance Program.
Only Facility Staff procedures are zecpxired to be reviewed by the PNSRC and NSDRC.
D.C COOK UNIT 2 6-13 Punendnant No.
10/PBAEKT
AQHINISTRATM"CXM.'ROLS
- 6. 9 REPORHNG REQUIHENWIS 6.9.1 In addition to the applicable reporting requirem nts of Title 10, Code of Federal Regulations, the following reports shall be suhnitted to the Regional Administrator unless otherwise noted.
6.9.1.1 A smam~ report of plant startup and power escalation testing shall be suhnitted following (1) receipt of an operating license; (2) anendnent to the license involving a planned increase in power level; (3) installation of fuel that has a different design or has been manufactured by a different fuel supplier; and (4) modifications that may have significantly altered the nuclear, thermal, or hydraulic performance of the plant.
6.9.1.2 The startup report shall address each of the tests identified in the FSAR and shall include a description of the measured values of the operating conditions or characteristics obtained during the test program and a canparison of these values with design predictions and specifications.
Any corrective actions that were required to obtain satisfactory operation shall also be described.
Any additional specific details required in license conditions based on other cxmnitments shall be included in this report.
6.9.1.3
. Startup reports shall be suhnitted within (1) 90 days following ccmpletion of the star~ test program; (2) 90 days following resumption or t of caarercial paver operation; or (3) 9 rmnths following initial criticality, whichever is earliest. Ifthe Startup Report does not cover all three events (i.e., initial criticality, canpletion of startup test program, and resumption or axaencement of cxxraercial D.C. GXK UNIT 2 11/PBAHET 6-14 Amendment No.
SPECIAL REPORrS 6.9.2 Special reports shall be suhnitted to the Attention of the Document Control Desk U. S. Nuclear Regulatory Camnission (Washington, D.C. ?0555),
with copies to the Region IIIAdministrator and the Resident Inspector at the D.C. Cook Nuclear Plant within the time period specified for each report.
These reports shall be suhnitted covering the activities identified below pursuant to the requhments of the applicable reference specification:
ao Inoperable Seismic Monitoring Instrumentation, Specification 3.3.3.3.
b.
Seismic Monitoring Instnznentation Actuated, Specification 4.3.3.3.2.
Ci d.
e.
g Inoperable Meteorological Monitoring Instrumentation, Specification 3.3.3.4.
Inoperable Fire Detection Instrumentation,
,Specification 3.3.3.7 (Unit 1) and 3.3.3.8 (Unit 2).
High Specific ActivityIn RCS Coolant, Specification 3.4.8.
RCS Pressure Transient Mitigated By RHR Safety Valve Or KS Vent(s),
Specification 3.4.9.3.
Sealed Source Leakage In Excess Of Limits, Specification 4.4.7.1.3 (Unit 1) and 4.7.8.1.3 (Unit 2).
h.
ECCS Actuation, Specifications 3.5.2 and 3.5.3.
Inoperable Fire Suppression
- Systems, Specifications 3.7.9.1, 3.7.9.2, 3.7.9.3, 3.7.9.4, and 3.7.9.5.
Inoperable Fire Rated Assemblies, Specification 3.7.10.
k.
n.
oe Excessive Releases Of Radioactivity, Specifications 3.11.1.2, 3.11.1.3, 3.11.2.2, 3.11.2.3, 3.11.2.4, and 3.11.4.
Inoperable Solid Radwaste System, Specification 3.11.3.
Excessive Level Of Radioactivity In Quarterly Environmental Sample, Specification 3.12.1 (Action b).
MilkAnd Vegetable Samples Not Available, Specification 3.12.1 (Action c).
Greater Calculated Dose Or Dose Cmmitment Identified By Land Census, Specification 3.12.2 (Actions a 6 b).
p.
Violation of Safety Limit, Specification 6.7.1.
D. C.
OOCK UNITS 1 and 2 15/PBMm 6-19 Amendment No.