ML20097H332
| ML20097H332 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 06/09/1992 |
| From: | Marsh L Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20097H335 | List: |
| References | |
| NUDOCS 9206260088 | |
| Download: ML20097H332 (16) | |
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9 CONSUMERS POWER COMPANY DOCKET NO. 50-255 PAllSADES PLANT AMENDMENT TO FACILITY OPERATING LICEN E Amendment No. 1E License No. DDR-20 1.
The Nuclear Regulatory Comission (the Commission) has found that:
A.
The application for amendment by Consumers Power Company (the licensee) April 2, 1990 and July 15, 1991; as amended Sept-ber 27, 1990, and December 20, 1991, respectively, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; 8.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public; and (ii) that such activities will be conducted in compliance with the Comission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to the license amendment and Paragraph 2.C (2) of Facility Operating License No. DPR-20 hereby issued to Consumers Power Company (the licensee or CPCo) to read as follows:
l 08CK05000255 08 920609 PR P
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. Tgchnical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.146. are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of~ issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
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7e L. B. Marsh, Director Project Directorate 111-1 Division of Reactor Projects Ill/IV/V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
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ATTACHMENT T0-LICENSE AMEllDMENT NO. 146
- FACILITY OPERATING LICENSE NO. DPR-20 DOCKET NO. 50-2M -
Revise Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages. The revised pages are identified by the amendment number and contain marginal lines indicating the area of change.
REMOV(
INSERT 3-40d 3-40d 3-40e 3-40e 134 3-134 6-5
. 6-5 6-Sa 6-Sa 6-6 6-6 i
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TABLE 3.6.1 CONTAINMENT PENE1 RATIONS AND VALVES SYSTEM NAMP. AND VALVE PEN NUMBER SERVICE LINE SIZEL ID NO REMARKS-39 CONTA:" MENT HEATING CV-1503 Auto isolation valve; SYSTEM (4")
Blind flange in.
required. closure place during time -'25 seconds
. power operation 40 PRI-C001 ANT SYSTEM CV-1910 Auto isolatton valve; SAMPLE LINE (%")
CV-1911-required closure time
'25 seconds-40A H," MONITOR
'SV-2414A
. Auto isolation valve;
() )
SV-24148 required closure time - 25 seconds 408
($" MONITOR 11 SV-2412A Auto isolation valve; I
)
SV-24128 required closure time - 25 seconds 41 DEGASiflER PUMP CV-1004 Auto isolation valve; DISCilARGE (3")
CK-CRW407 required closure time - 25 seconds 42 DEMINERAllZED CV-0155 Auto isolation valve; WATER TO QUENCH CK-V01558 required' closure TANK (2")
time - 25 seconds 44 CONTROLLED BLEED-Off CV-2083 Auto isolation valve; FROM RCP'S CV-2099 required closure (3/4")
time - 25 seconds 46 CONTAINMENT VENT CV-1101 Auto isolation valve; HEADER (4")
CV-Il02 required closure time - 25 seconds 3-40d.
Amendment No. //jt,}g,
TABLE 3.6.1 CONTAINMENT PENETRAll0NS AND VALVES SYSIEM NAME AND VALVE PEN NUMBER SERVICE LINE SIZE ID NO REMARKS 47 PRIMARY SYSTEM CV-1002 Auto isolation valve; ORAIN TANK PUMP CV-1007 required closure SUCTION (4")
time - 25 seconds 43 CIEAN WASTE CV-1038 Auto isolation valve; RECEIVER TANK CV-1036 required closure CIRCULATION PUMP time - 25 seconds SUCTION (6")
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52 CONTAINMENT SUMP CV-Il03 Auto isolation valve; DRAlH TO DIRTY WASTE CV-Il04 required closure TANK (4")
time - 25 seconds 55 S/G (E-508)
CV-0738 Auto isolation valve; RECIRCULATION (4")*
required closure time = 25 seconds 67 CLEAN WASTE CV-1037 Auto isolrdon valve; RECEIVER TANK PUMP CK-CRW408 required c.ssure RECIRC (3")
time - 25 seconds I
68 AIR SUPPLY 10 CV-1813 Auto isolation valve; l
AIR ROOM (12")
CV-1814 required closure time - 25 seconds 69 CLEAN WASTE CV-1045 Auto isolation valve; RECEIVER 1ANK PUMP CV-1044 required closure SUCTION (4")
time - 25 set.onds 1
l OPenetration line size; isolation valves are 2-inch.
3-40e Amendment No. J/$,1 W
(
- 146, I
L _ _ ___
. 25 ALTERNATE SHUTOOWN SYSTEM i!MIT'NG CON 01 TION FOR OPEDATION
- .25.1 The Alternate Shutdown Systes instrumentation and :omponents shown in Table 3.25.1 shall be OPERABLE.
Operability shall be demonstrated by performing the surveillances in accordance with Section 4.21.
l 1PLICABillTY:
Reactor coolant temperature 2 325'F.
ACTION:
a.
With less than th " Minimum Equipment
- in Table 3.25.1 Operable, restore the inoperable equipment to Operable within 7 days, or provide-equivalent shutdown capability and restore the inoperable equipment to Operable within 60 days; or be in Hot Shutdown within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and Cold Shutdown within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, b.
The provisions of Specification 3.0.3 and 3.0.4 do not apply, fjL5il The operability of the Alternate Shutdown System ensures that any fire will not preclude achieving safe shutdown.
The Alternate Shutdown System components are independent of areas where a fire could damage systems normally used to shut down the reactor..This capability is consistent with Regulatory Guide 1.97 and Appendix R to 10CFR50.
3-134 Amendment No. J22,146, 1
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ADMINISTRATIVE CONTROLS 6.4 TRAINING 6.4.1 A retraining and replacement training program for the plant staff shall be maintained and shall meet or exceed the reg'airements and recommendations of Section 5.5 of ANSI N18.1-1971 and Appendix "A* of 10 CFR Part 55.
6.4.2 The Fire Brigade training program shall be maintained and shall, as practicable, meet or exceed the requirements of Section 27 of the NFPA Code-1975.
Fire origade training drills shall be held at least quarterly.
6.5 REVIEW AND AUDIT 6.5.1 PLANT REVIEW COMMITTEE (PRC) 6.5.1.1 FUNCTION The Plant Review Ccmmittee (PRC) shall function to advise the Plant L
General Manager on all matters related to nuclear safety.
6.5.1.2 COMROSITION The PRC is composed of ten regular members from either the Palisades staff or the Nuclear Engineering and Construction Organization (NECO) staff.
The PRC members shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions.
The PRC shall include representatives from the Operations, Radiological Services, Maintenance and Engineering Departments.
The members shall be designated in administrative procedures by the Plant General
. Manager. The Plant General Manager shall also designate the Chairman and alternates in writing.
6.5.1.3 ALTERNATES Alternate members of the PRC shall be appointed in writing by the PRC Chairman to serve on a temporary basis.
No more than two alternates shall participate as voting members at any one time in PRC activities.
1 6-5 Amendment No. J$,ff,75,Jpp,J17,JJ9 3c5, l
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4 ADH]NISTRATIVE CONTROLS 6.5.1:4 MEETING FRE0jlMCl The PRC'$ hall meet at least once per calendar month with special meetings as required.
6.5.1.5 000 RUM A quorum of the PRC shall consist of the Chairman or alternate, and four nembers or alternates.
6.5.1.6 RESPONSIBillTIES The PRC shall be responsible for nuclear safety review of:
a.
All procedures and programs specified by Specification 6.8 and changes thereto, and any other procedures or changes thereto as determined by the Plant General Manager to affect nuclear safety; all proposed tests or experieents that affect nuclear safety; all proposed changes or modifications to plant systems or equipment that affect nuclear safety; and the Site Emergency Plan, b.
All proposed changes to Operating License and Technical Specifications.
c.
Results of investigations of all violations of the Technical Specifications.
(A report shall be prepared covering evaluation and recommendations to prevent recurrence and be forwarded to the Vice President - NOD ar.d to the Director, Nuclear Performance Assessment Department (NPAD).)
d.
Plant operations to detect potential safety hazards.
Reports of special reviews and investigations as requested by the e.
Plant General Manager or NPAD.
l f.
All reportable events as defined in Section 6.9.2.
l g.
All items identified under Specificatior 6.5.3.4 as significant to nuclear safety.
h.
Monthly reports from Plant Safety and Licensing, i.
Nuclear industry operating experience.
l PRC review of the above items may be performed by routing, subject to the requirements of Specification 6.5.1.7.
PRC may delegate review of item a. to Plant Safety and Licensing as described in Specification 6.5.3.
6-Sa Amendment No. JES, J27,145
ADMINISTRATIVE CONTROLS 6,5.1.7 AUTHORITY The PRC shall:
a.
Recommend in writing to the Plant General Msnager approval or disapproval of items considered under Specifications 6.5.1.6.a.
through 1, above.
l b.
Render determinations in writing with regard to whether or not each item considered under Specifications 6.5.1,6.a, b, c and g 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 Vice President - Nuclear Operations and to the Nuclear Performance Assessment Department of any disagreements between the PRC and the Plant General Manager; however, the Plant General Manager shall have responsibility for the resolution of such disagreements pursuant to Specification 6.1.1 above.
The PRC Chairman may recommend to the Plant General Manager approval of those items identified in Specification 6.5.1.6 above based on a routing review provided the following conditions are met: (1) at least five PRC members including the Chairman and no more than 2 alternates, shall review the item, concur with determination as to whether or not the item constitutes an unreviewed safety question, and. provide written comments on the item; (2) all comments shall be resolved to the satisfaction of the rev.' ewers providing the comments; and (3) if the PRC Chairman determines that the comments are significant, the item (including cemments and resolutions) shall be recirculated to all reviewers for additional comments.
The item shall be reviewed at a PRC meeting in the event that:
(1) Comments are not resolved; or (2) the Plant General Manager overrides the recommendations of the PRC; or (3) a proposed change to
- the Technical Specifications involves a safety limit, a limiting
. safety system setting or a limiting condition for operation; or (4) the item was reportable to the NRC.
6.5.1.8 RECORDS The PRC shall maintain written minutes of each PRC meeting and shall provide copies to the NPAD.
l l
l 6-6 l
- endment No. 1,4, 15, 95, R$, 155, 121
- 1c6, 1
1
1 ADMINISTRATIVE CONTROLS 6.5.2*
NUCLEAR PERFORMANCE ASSESSMENT DEPARTMENT (NPAD) j 6.5.2.1 FUNCTION The Nuclear Performan'.e Assessment Department (NPAD) shall function
(
to provide independent review of activities in the areas of:
a.
Nuclear power plant operation F
b.
Nuclear engineering c.
Chemistry and radiochemistry d.
Metallurgy e.
Instrumentation and control f.
Radiological safety g.
Mechanical and electrical engineering h.
Quality assurance practices 6.5.2.2 COMPCSITION
-The NPAD shall include the Director, who reports to the Vice President - N00, and a full-time staf f of Nuclear Performance Specialists reporting to the Diretter.
The Director and the Nuclear Performance Specialists shall meet or exceed the qualifications described in Section 4 of ANSI /ANS 3.1-1987.
The NPAD shall have no direct responsibility for activities subject to its review.
6.5.2.3 CONSULTANTS If sufficient expertise is not available within NPAD to review particular issues, the NPAD shall have the authority to utilize 4
consultants or other qualified organizations for expert advice.
6.5.2.4 RESP 0NSIBitITIES 6.5.2.4.1 REVIEW The NPAD shall review:
I a.
The safety evaluations for:
- 1) changes to procedures, equipment or systems, and 2) tests or experiments completed under the provisions of 10 CFR 50.59 to verify that such actions do not constitute an unreviewed safety question.
b.
Proposed changes to procedures, equipment or systems which involve an unreviewed safety question as defined in 10 CFR 50.59.
6-6a Amedment No. //, JE, E), EE, JEE, J27,146 a
4 G LSTAaT!VE CONTPOLS 6.5.2.4.1 REVIEW (Continued) c.
Proposed tests or experiments which involve an unreviewed safety question as defined in 10 CFR 50.59.
d.
Proposed changes to Technical Specifications or the Operating
- License, e.
Violations of codes, regulations, orders, Technical Specifications, license requirements, or of internal procedures
(
or instructions having nuclear safety significance.
f.
Significant operating abnormalities or deviations from normal and expected performance of uni' equipment that affects nuclear s a fety, g.
All reportable events having nuclear safety significance, h.
All recognized indications of an unanticipated deficiency in some aspect of design or operation of structures, systems, or components that could affect nuclear safety.
i.
Reports and meeting minutes of the Plant Review Committee.
6.5.2.4.2 MOITS Audits of operational nuclear safety-related facility activities shall be performed by the NPAD staff under the cognizance of the Nuclear Performance Specialists.
These audits shall encompass:
a.
The conformance of plant 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 entire facility staff at least once per 12 months.
The performance of activities required by the Quality Assurance c.
Program Description for Operational Nuclear Power Plants (CPC-2A) to meet the criteria of 10 CFR 50, Appendix B at least once per 24 nonths.
d.
The Site Emergency Plan and irrplcmenting procedures at least once per 12 months.
The Site Security Plan and implementing procedures (as required e.
by the Site Security Plan) at least once per 12 months.
6-7 Amendment No. ZA, /J, JRE, J27, g,
ADMINISTRATIVE CONTR0ts 6.5.2.4.2 AUD111 (Continued) f.
Any other area of plant operation considered appropriate by l
NPAD or the Vice President - Nuclear Operations, g.
The plant Fire Protection Program and implementing procedures at least once per 24 months.
h.
An independent fire protection and loss prevention inspection and audit to be performed annually utilizing either qualified offsite i :ensee personnel or an outside fire protection firm.
i.
An inspection snd audit of the fire protection and loss prevention program to be performed by an outside qualified fire consultant at intervals no greater than 3 years.
j.
Radiological environmental monitoring program and the results thereof at least once per 12 months.
k.
The OFFSITE DOSE CALCULATION MANUAL and ' implementing procedures for processing and packaging of radioactive wastes at least once per 24 montns.
1.
The PROCESS CONTROL PROGRAM and implementing procedJres for processing and packaging of radioactive wastes at least once e
per 24 months.
Audit reports encompassed by Soecification 5.5.2.4.2 above shall be forwarded to the Director NPAD, and Management positions l
responsible for the areas audited within thirty (30) days ar~ter completion of the audit, d
6.5.2.4.3 NPAD review of the subjects in Specifications 6.5.2.4.1 and 6.5.2.4.2 shall be performed by an assigned Nuclear Performance Specialist selected on the basis of his technical expertise relativa to the subject being reviewed.
If the assigned Nuclear Performance Specialist determines the need for interdisciplinary review, a committee consisting of the Director, NPAD, or his designate, and at least four Nucle.
Performance Specialists, shall be assigned.
6.5.2.5 AUTHORITY The NPAD shall report to and advise the Vice President - N00 of significant findings associated with those areas of responsibility specified in Sections 6.5.2.4.1 and Section 6.5.2.4.2.
6-8 Amendment No. 75, E.6, JEE, 127,1 u ep -
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ADMINISTRATIVE CONTR3ts 6.5.2.s RECO'tDS Records of NPAD activiMes shall be maintained.
Reports shall be l
prepared aiid distributed as indicated below:
a.
The results of reviews, performed pursuant to Section 6.5.2.4.1 and Section 6.5.2.4.2, shall be reported to the Vice President N00 at least monthly.
b.
A report assessing the overall nuclear safety performance of Palisades shall be provided to senior Consumers Power Company management annually.
6.5.3 PLANT SAFETY AMD M Q LS,1!Js 6.5.3.1 FUNCTION The Plant Safety and Licensing organization shall function to examine proposed changes in design or operati:3 and such other matters as the PRC may assign to identify issues significant to nuclear safety and recommend nuclear safety improvements, 6.5.3.2 COMPOSITION The Plant Safety and Licensing staff shall be composed of at least five experienced technical staff, reporting to the Plant Safety and Licensing Director, to carry out these functions.
6.5.3.3 RESPONSIBILITIES The Plant Safety and Licensing staff may provide nuclear safety
-review as delegated by PRC for:
a.
Procedures, programs and changes thereto identified in Specification 6.8 and any additional procedures and changes thereto identified by the Plant General Manager as significant to nuclear safety.
b.
All proposed tests or experiments.
Ali proposed changes or modifications to plant systems or c.
equipment.
d.
The Site Emcrgency Plan.
l 6-9 Amendment No. 75, E5, JSE, J27
- 146, I
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ADMINISTRATIVE CONTROLS 6.5.3.4 AUTHORITY The Plant Safety and Licensing staff shall determine those issues significant to nuclear safety which require review by the Plant Review Committee from items :onsidered under Specification 6.5.3.3.a through d.
For those items not referred to PRC, Plant Safety and Licensing shall recommend in writing to plant management approval or disapproval of items considered under 6.5.3.3.
6.5.3.5 RECORDS Reports of Plant Safety and Licensing activities pursuant to Specification 6.5.3.3 shall be submitted monthly to PRC.
6.6 IDeleted) 6.7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a safety limit is violated:
a.
The reactor shall be shut down 'amediately and not restarted until the Commission authorizes resumption of operation (10 CFR 50.36(c)(1)(1)(A)).
b.
The safety limit violation shall be reported within I hour to the Commission in accordance with 10 CFR 50.36, as well as to the Vice President - Nuclear Operations and to the NPAD.
l c.
A report shall be prepared in accordance with 10 CFR 50.36 and 6.9 of this specification.
(The safety limit violation and the report shall be reviewed by the PRC.)
d.
The report shall be submitted within 14 days to the Commission (in accordance with the requirements of 10 CFR 50.36), to the Vice President - Nuclear Operations and to the NPAD.
l 6-10 Amendment No. JJ, 75, 127, 146 r
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ADMINISTRATIVE CONTROLS i
6.9.3.3 Special Recorts a.
Special Reports shall be submitted to the NRC covering the activities identified below pursuant to the requirements of the 1
applicable refererced specifications; i
Specift:ation Reporting Area Reference Due Prestressing, Anchcrage, 4.5.4 90 Days After Liner and Penetration 4.5.5 Completion of Tests the Testa
- A test is considered to be complete after all associated mechanical, chemical, etc., tests have been completed.
b.
Special reports shall be submitted in accordance with 10CFR50.4, within the time period specified for each report.
6.10 RECOPD RETENTION i
In addition to the applicable record retention requirements of Title 10, Code of federal Regulations, the following records shall be retained for at least the minimum period indicated:
6.10.1 The following records shall be ratained for at least five years:
Records and logs of facility operation cover'79 time interval a.
at each power level.
b.
Recerds and logs of principal-maintenance activities, inspections, repair and replacement of pri.1c'pai items of equipment related to nuclear safety.
c.
All reportable events as defined in Section 6.9.2.
l d.
Records of surveillance activities, inspections and calibrations required by these Technical Specifications.
b 3 26 Arendment No. JJ, E/, SJ, 198
'T
l A PINISTRATIVE CONTROLS RECORD RETENTION (Contd)
Records of changes made to the procedures required by e.
Specification 6.8.1.
f.
Records of radioactive shipments.
g.
Records of sealed source leak tests and results, h.
Records of annual physical inventory of all source material of record.
6.10.2 The following records shall be retained for the duration of the Facility Operating License:
a.
Record and drawing changes reflecting facility design modifications made to systems and equipment described in the Final Safety Analysis Report.
b.
Records of new and irradiated fuel inventory, fuel transfers and assembly burnup histories.
c.
Records of monthly radiation exposure for all individuals entering radiation control areas.
d.
Records of gaseous and liquid radioactive material released to the environs.
Records of transient or operational cycles for those facility e.
components designed for a limited number of transients or cycles.
f.
Records of inservice inspections performed pursuant to these Technical Specifications, g.
Records of Quality Assurance activities required by the QA Program Description, h.
Records of reviews performed for changes made to proceouces or equipment or reviews of tests and experiments pursuant to 10 CFR 50.59.
i.
Records of meetings of the PRC and reviews performed by tpg, l
j.
Records of monthly facility radiation and contamination surveys.
6 27 Amendment No. 15, pf$ff1/f$1/$/J9/1$/$9,99,195. g,
-