ML20246D836
| ML20246D836 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 08/16/1989 |
| From: | Yandell L Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20246D841 | List: |
| References | |
| NUDOCS 8908280293 | |
| Download: ML20246D836 (16) | |
Text
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UNITED STATES '
L g-NUCLEAR REGULATORY COMMISSION l
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-l WASHINGTON, D. C. 20555
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CONSUMERS POWER COMPANY L
PALISADES PLANT DOCKET NO. 50-255 AMENDMENT TO PROVISIONAL OPERATING LICENSE l
Amendment No.127 License No. DPR-20 1.
The Nuclear Pegulatory Comission (the Comission) has found that:
A.
The application for amendment by Consumers Power Company (the licensee)dstedSeptember 23, 1988 and supplemented by a letter dated January 16, 1989, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
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 (1) that the activities authorized by this amdndment 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; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
1 8908280293 890816 e
{DR ADDCK 05000255 k@l PNU
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2.
Accordingly, the license is amended by changes to the Technical l
Specifications as indicated in the attachment to this license amendment and Paragraph 3.B. of Provisional Operating License No. DPR-20 is hereby amended to read'as follows:
Technical Specifications l-l The Technical Specifications contained in Appendices A and B,
- as revised through Amendment No.327m. are hereby incorporated in the license. The licensee shall operate the facility l
in accordance with the Technical Specifications.
3.
This license amendment. is effective as of the date of its issuance
.and shall be implemented not later then. September 30, 1989.
FOR.THE NUCLEAR REGULATORY COMMISSION f
f.
t QQl(
Lb/
wrenceY(andell,ActingDirector Project Directorate - 111-1 Division of Reactor Projects - III, IV, Y and Special Projects Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: August 16, 1989
7 ATTACHMENT TO LICENSE AMENDM2NT NO. 127 PROVISIONAL OPERATING LICENSE NO. DPR-20 l'
DOCKET NO. 50-255 Re!/ise Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages. The revised pages are identified by the r,tutioned arcendment number and contain marginal lines indicating the area of citenpe.
REMOVE INSERT
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vi vi vii vii 6-la 6-1e 6-Ib 6-lb 6-5 6-5 6-Sa 6-Sa 6-6 6-6 6-6a 6-6a 6-7 6-7 6-8 6-8 6-9 6-9 6-10 6-10 6-10a 6-10e
3 PALISADES PLANT TECHNICAL SPECIFICATIONS TABLE OF CONTENTS - APPENDIX A K
SECT 1,0N DESCRIPTION
~PAGE NO 4.0-
~ SURVEILLANCE REQUIREMENTS (Continued) 4.24.6' Gaseous Waste System.
4-91 4.24.7 Solid Radioactive Waste
'4-91 4.24'.8 Total Dose' 4-91 Table'4.?.4-l' Radioactive' Liquid Effluent. Monitoring Instrumentation Surveillance Requirements 4-92
~ Table 4.24-2 Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance' Requirements ~
4-93 Table 4.24-3. Radioactive Liquid Waste Ocmpling and Analysis Program 4-95 Table 4.24-5 Radioactive Gaseous Waste Sampling and Analysis Program 4-97 5.0:
DESIGN FEATURES.
5-1 5.1-SITE 5-1 5.2-CONTAINMENT DESIGN FEATLTGS '
5-1 5.2.1 Containment 5tructures 5-1 5.2.2 Penetrations 5-2 5.2.3 containment Structure Cooling Systems 5-2 5.3 NUCLEAR STEAM SUPPLY SYSTEM (NSSS) 5-2 5.3.1-
-Primary Coolant System 5-2 5.3.2 Reactor Core and Cortrol 5-3 5.3.3 Emergency Core Cooling System 5-3
~5.4 FUEL STORAGE' 5-4
-5.4.1_
New Fuel Storage-5-4 5.4.2 Spent Fuel Storage 5-4a Figure 5-1 Site Environment TLD Stations 5-5 l
6C
~ADMINISTRIT7VE CONTROLS 6-1 L.
f<.1 1 RESPONS1P!LI1T 6-1 6.2 ORGANIZATION 6-1 R
6.2.1 Offsite and Onsite Organizations 6-1
'5.2.2 Plt.nt ' Staf f 6-la i
6.3 PLANT STAFF QUALIFICATIONS 6-lb
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j is
_ _ Table 6.2-1 Minim n Shift Crev Oir;ouition 6-4 1
l 6.4 TRA7N7M 6 ~5
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h vi Amendment No S$ 195. 10E,127 TSP 0189-0001-NLO4 l
i.
PALISADES PLANT TECENICAL SPECIFICATIONS TABLE OF CONTENTS - APPENDIX A SECTION DESCRIPTION PAGE NO 6.0 ADMINISTRATIVE CONTROLS (Continued) 6.5 REVIEW AND AUDIT 6-5 6.5.1 Plant Review Committee (PRC) 6-5 6.5.2 Nuclear Safety Services Department (NSSD) 6-6a
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6.5.3 Plant Safety and Licensing 6-9
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6.6 (Deleted) 6-10 6.7 SAFETY LIMIT VIOLATION 6-10 6.8 PROCEDURES 6-10a /
6.9 REPORTING REQUIREMENTS 6-11 6.9.1 Routine Reports 6-11 6.9.2 Reportable Events 6-12 6.9.3 Other Reporting Requirements 6-18 6.9.3.1 Routine Reports 6-18 6.9.3.1.A Radioactive Effluent Releases 6-18 6.9.3.1.B Annual Radiological Environmental Operating Report 6-24 6.9.3.2 Nonroutine Reports 6-25b Table 6.9-1 Environmental Radiological Monitoring Program Summary 6-25c 6.9.3.3 Special Reports 6-26 6.10 RECORD RETENTION 6-26 6.11 RADIATION PROTECTION PROGRAM 6-28 6.12 HIGH RADIATION AREA 6-28 6.13 (Deleted) 6-33 6.14 (Deleted) 6-33 6.15 SYSTEMS INTEGRITY 6-33 6.16 IODINE MONITORING 6-33 6.17 POST ACCIDENT SAMPLING 6-34 6.18 0FFSITE DOSE CALCULATION MANUAL (ODCM) 6-35 6.19 PROCESS CONTROL PROGRAM (PCP) 6-35 6.20 MAJOR MODIFICATIONS TO RADI0 ACTIVE LIQUID, JASE00S AND SOLID WASTE TREATMENT SYSTEMS 6-36 6.21 SEALED SOURCE CONTAMINATION 6-37 6.22 SECONDARY WATER CHEMISTRY 6-38 i
i I
l vii Amendment No. JPE, 119,127 TSP 0189-0001-NLO4
- ADMINISTRATIVE CONTROLS
- X l
6.2.2--
PLANT STAFF'(Continued) 1 f.
Administrative procedures shall limit the working hours of J
[
Plant; staff who perform safety-related. functions.
In the event,that. overtime.is used, thelfo11'owing guidelines
^ hall-be followed:
s A.
An individualzshall not be permitted.to work more than
'16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> straight (excluding shift turnover time).
B.
An individual shall'not be permitted to' work-more than 16 hour1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br />s:in any 24-hour period, nor more,than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in_any 48-hour period, nor.more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in any seven-day period (all excluding shift turnover.-time).-
C.' A break of.at least eight hours shall be allowed between work periods (including shift turnover. time).
~D..Except during extended shutdown' periods the use of; overtime:should be considered on an individual basis and r.ot-for the entire staff on a' shift.
Deviations from the overtime-guidelines;shall be authorized by the Plant General' Manager'or his Alternate. The basis for. granting the deviation shall be documented. Routine deviations are not to be authorized.
Individual overtime will be reviewed monthly by'the Plant General Manager or his designee to assure that excessive hours have not been assigned.
6.2.3 (DELETED).
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i 6-1a Amendment No. 75, 175.127
- TSP 0189-0001-NLO4
m;
..y.
E ADMINISTRATIVE CONTROLS r,
< 6.243.2 (Continued).
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- g (DELETED)-
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4 6.3 PLANT STAFF QUALIFICATIONS
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6.3.I' Each member of the plant staff shall meet or exceed the minimum qualifications of: ANSI N18.1-1971 for comparable.
positions.
- 6 3.2 -
.The. Plant Health Physics Superintendent shall meet or exceed
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the: qualifications of Regulatory Guide 1.8,. September 1975.*
- 6. 3. 3'
.The Shift Technical'Advbor shall havs s bachelor's degree or equivalent and the Shift Engineer shall nave a bachelor's degree in a scientific-or engineering discipline with specific
. training in plant design and/or operations, and response and analysis of the plant for transients and accidents. The Shift.
Engineer shall hold a Senior Operator License.
6.3.4 The Plant Safety and Licensing staff who perform the reviews-
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specified in 6.5.3 shall-meet or exceed the minimum
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' qualifications of ANS 3.1 - 1987, Section 4.7.1'and 4.7.2.
A.
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-Senior Reactor Operator License or certification shall be
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considered equivalent to a bachelors degree for the purpose
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of this specification for no more than two-individuals.
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1
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- A f
- For the purpose of this section, " Equivalent," as utilized in llegulatory l
Guide 1.8 for the bachelor's degree requirement, may be met with fou:
-years of'any one or. combination of the following:
(a) Formal schooling in science or engineering, or (b) operational or technical experience /
training in nuclear power.
l 6-lb Amendment No. 32, 57, 57, 55, 75, 105,127
. TSP 0189-0001-NLO4
_b
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s ADMINISTRATIVE CONTROLS
.. 6.4.
TRAINING.
6.4.1-A' retraining:and replacement training program for,thel plant staff shall-be maintained under the' direction of the Executive Director
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~ of-Energy Supply Planning, Training and Administration,'and shall meet or exceed the requirements and recommendations of Section 5.5 of ANSI N18.1 '971 and Appendix "A" of 10 CFR Part 55.
6.4.2
-The Directorfof Property. Protection is' responsible for the;
' development, revision, approval ~and. implementation of the Fire Brigade. training program. This training shall,.as practicable, meet or exceed the-requirements of.Section 27 of the NFPA' Code-1975. Fire Brigade training drills shallibe held at least.
quarterly.
L.-
6.5 REVIEW AND AUDIT' 6.5.1
. PLANT REVIEW COMMITTEE'(PRC)
- 6.5.1.1 FUNCTION
-The-Plant Review Committ'ee (PRC) shall function to advise the' l
Plant General Manager on all matters related to nuclear-safety.
l l.
6.5.1.2 COMPOSITION The PRC.shall be composed of:
Chairman: PiantGeneralManager
=/
Member:
Operations Manager
- Member:
Engineering and Maintenance Manager
- Member:
Radiological Services Manager
- Menber:
Plant Safety and Licensing Director *
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Member:
Reactor Engineering Superintendent.
Member:
Operations Superintendent Member:
Instrumentation and Control-Superintendent Member:
Shift Superviser er Bhift Lngtneer(rJ(1)
')
- mry verie as Designated Alterrate for the Chairman 6.5.2.3 ALTERNATES F '
Alte;ntia members of the PRC shall be appointei4 in writing by the PRC Chr.irman to serve en a,emporsry basia. No more than two i
alternatus sha31 participate as voting mest e rs at any one time in PEC activities Memberu identified vith a asterisk (*) above may M'
function as t'u? Designated Alternate for the Chairman, and in so doing, are not considered alternate members for voting purposes.
6-5 Amendment No. 16, #5, 75, 105,127
. TSP 0189-0001-NLO4
ADMINISTRATIVE CONTROLS 6.5.1.4 MEETING FREQUENCY The PRC shall meet at least once per calendar month with special meetings as required.
6.5.1.5 QUORUM A quorum of the PRC shall consist of the Chairman and four members (including alternates).
6.5.1.6 RESPONSIBILITIES The PRC shall be responsible for nuclear safety review of:
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All procedures and programs specified by Specification 6.8
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a.
and changes thereto, and any other procedures or changes
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thereto as determined by the Plant General Manager to
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affect nuclear safety; all proposed tests or experiments
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that affect nuclear safety; all proposed changes or
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modifications to plant systems or equipment that affect
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nuclear safety; and the Site Emergency Plan.
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b.
All proposed changes to Operating License and Technical
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Specifications.
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c.
Results of investigations of all violations of the Technical
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Specifications.
(A report shall be prepared covering
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evaluation and recommendations to prevent recurrence and be
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forwarded to the Vice President - NOD and Nuclear Safety
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Service Department (NSSD).)
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d.
Plant operations to detect potential safety hazards.
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Reports of special reviews and investigations as requested
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e.
by the Plant General Manager or NSSD.
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- . All reportable events as defined in Section 1 4.
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g.
Al) items identified under Specification 5.5.3.4 as
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significant to nuclear safety
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h.
Monthly reports from Plant Safety and Licensing.
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j l'RC review of the abo e items. may be performet b3 routing,
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subject to the requirements of Specificatica 6.5.1.7.
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may de':. elate review of item r. to Plant Sefety and Licens.ng
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as described in Specification 6.5.3
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6-Sa Amendment No. 10f>,127 i
TSP 0189-0001-NLO4 L__
l' ADMINISTRATIVE CONTROLS 6.5.1.7 AUTHORITY The PRC shall:
Recommend in writing to the Plant General Manager approval a.
or disapproval of items considered under Specifications 6.5.1.6.a. through h. above.
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b.
Render determinations in writing with regard to whether or not each item' considered under Specifications 6.5.1.6.a, b,
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c and g above constitutes an unreviewed safety question.
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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 Safety
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Services Department of any disagreements between the PRC
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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
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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 >he reviewers providing the comments; and (3) if the PRC Chairman determines that the comments are significant, the item (including comments and resolutions) shall be ree?nculated to aff reviewers for additional comments.
1he f tem shall be reviewed at a F3C reeting in the event that:
(1) c>n,.nents sre not resolved; or (2) the Flaat General Manager overriles the recommendations of the PEC; or (3) a proposed
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change to the Technical Specifications involves a safety limit, a limiting safety system settirg or a limiting condition for operstion; or (4) the item was repostable to the NRC.
6.5.1.8 XICORDS The PRC shall maintain written minutes of each PRC meeting and i
shall provide copies to the FSSD.
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l l
6-6 Amendment No. 24, 75, E5, E6, 10E,127 TSP 0189-0001-NLO4 l
1
L.
ADMINISTRATIVE CONTROLS 6.5.2 NUCLEAR SAFETY SERVICES DEPARTMENT (NSSD) 6.5.2.1 FUNCTION
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L The Nuclear Safety Services Department (NSSD) shall function
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to provide independent review of activities in the areas of:
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a Nuclear power plant operation
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b.
Nuclear engineering
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c.
Chemistry and radiochemistry
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d.
Metallurgy
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e.
Nondestructive testing
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f.
Instrumentation and control
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g.
Radiological safety
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h.
Mechanical and electrical engineering
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- i. Administrative controls and quality assurance practices
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- j. Emergency Planning
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k.
Training
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6.5.2.2 COMPOSITION The NSSD shall consist of a full-time staff appointed by and
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reporting to the Vice President - NOD. NSSD staff shall have
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no direct responsibility for activities subject to their
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review.
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The NSSD staff shall meet or exceed the qualifications
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described in Section 4.7 of ANSI /ANS 3.1 - 1987.
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6.5.2.3 CONSULTANTS If sufficient expertise is not available within NSSD to review
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particular issues, the NSSD shall have the authority to utilize
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consultants or otter qualified organizations for expert advice.
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6.5.2.4 RESPONSIBILITIES l
6.5.2.4.1 REVIEV l
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The NSSD shall review:
a.
The stfety evaluations for:
- 1) cPanges to procecures,
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q equ,puent or systems, and 2) tests or experiments completed
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under the provisions of 10 CFR 50.59 to verity thtt such
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actions do not constitute an unrevieved saft.ty question.
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b.
Proposed changes to procedures, equipment or systems which
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involve an unreviewed safety question as defined in 10 CFR 50.59.
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1 6-6a 1
Amendment No. 24, 75, E3, EE,
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10E,.127 l
TSP 0189-0001-NLO4
ADMINISTRATIVE CONTROLS l
6.5.2.4.1 REVIEW (Continued)
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c.
Proposed tests or experiments which involve an
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l unreviewed safety question as defined in 10 CFR 50.59.
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d.
Proposed changes to Technical Specifications or the
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Operating License.
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Violations of codes, regulations, orders, Technical
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e.
Specifications, license requirements, or of internal
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procedures or instructions having nuclear safety
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significance.
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f.
Significant. operating abnormalities or deviations from
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normal and expected performance of unit equipment that
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affects nuclear safety.
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g.
All raportable. events having nuclear safety significance.
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h.
All recognized indications of an unanticipated deficiency
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in some aspect of design or operation of structures,
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systems, or components that could affect nuclear safety.
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- i. Reports and meeting minutes of the Plant Review Committee.
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6.5.2.4.2 AUDITS
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Audits of operational nuclear safety-related facility activities shall be performed under the cognizance of NSSD.
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These audits shall encompass:
The ccanformance of plant operation to pronsions a.
contained within the Technical Specif>::atiens and applicable li.ense con 6f tions at 1 :..st Sn:e per 12 n:onths.
b.
The performance, training and qualifications of the entire facility staff et least once per 12 months.
The perfoam.M e of A:tivities required by the Quality
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c.
Assurance o t gra,4 De-criptian for Operational Nuclear
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i r
Power Plents (C&2A) te ocet the criteriu of 10 Cfk 50,
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Appendix B a: lesst once pc.r.; 4 saoriths.
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d.
The Site Emergency Plau and implementing pra.edures at least once per le' mc.nths.
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e.
The f1te Security Plan and implementing procedures (as required by the Site Security Plan) at least once per 12 months.
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6-7 Amendment No. 24, 75, 10E,.12.7 TSP 0189-0001-NLO4
______________________________ _ _ _ o
l J.
k ADMINISTRATIVE CONTROLS c6.5.2.4.2. AUDITS (Continued)'
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p
- f -Any other. area of plant operation considered appropriate
'by NSSD or the Vice President.- Nuclear Operations.
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g.
The plant Fire Protection Program'and, implementing-procedures at least once per.24 months.
b.
An independent' fire protection and loss prevention
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inspection and audit to be performed annually utilizing
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either qualified offsite licensee personnel or an outside fire protection firm.
i.
An inspection'and audit of the fire protection and. loss prevention program'to be performed by an outside
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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.
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k.
The OFFSITE DOSE CALCULATION MANUAL and implementing
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procedures for processing and packaging of radioactive
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wastes'at least once per 24 months.
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1.
The PROCESS CONTROL PROGRAM and implementing procedures
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for processing and packaging of radioactive wastes at
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least once per 24 months.
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Audit reports encompassed by Specification 6.5.2.4.2 above
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shall be forwarded to the NSSD, and Management positions
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= responsible for~the areer audited within thirty (30) days efter c:smpietion nf the audat.
6.5.2.2.3. N'1SD review of the subjects in Specifications 6.5.2.4.1 and 6.5.3.4.2 shall be cerried ont by an assigned Iced reviewer
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l selected on the basis of his technical expertise relative to
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the subje:t being reviewed. A second-level review chall also
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l.;
he performed.
If either the lead reviewer or second-leve]
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' reviewer determines the need for interdisciplinary review.
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additional revievers shall be assigned.
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L 6.5.2.5
. AUTHORITY
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The NSSD shall report to and advise the Vice President - NOD
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of significant findings associated with those areas of
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responsibility specified in Sections 6.5.2.4.1 and Section
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6.5.2.4.2.-
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6-8 Amendment No. 75, 55, J$$,127 TSP 0189-0001-NLO4 1
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ADMINISTRATIVE CONTROLS 6.5.2.6
' RECORDS' Records of NSSD activities shall be maintained. Reports shall
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be prepared and distributed as indicated below:
The results of reviews, performed pursuant to Section
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a.
6.5.2.4.1 and Section 6.5.2.4.2, shall be reported to the
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Vice President - F0D at least monthly.
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b.
A report assessing the overall nuclear safety performance
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of Palisades shall be provided to senior Consumers Power
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Company management annually.
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6.5.3 PLANT SAFETY AND LICENSING
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6.5.3.1 FUNCTION
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The Plant Safety and Licensing organization shall function to
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examine industry operating experience and proposed changes
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in design or operation to identify issues significant to
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nuclear safety and recommend nuclear safety improvements.
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6.5.3.2 COMPOSITION
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The Plant Safety and Licensing staff shall be composed of at
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least five experienced technical staf:, reporting to the Plant
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Safety and Licensing Director, to carry out these functions.
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6.5.3,3 RESPONSIBILITIES
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The Plant Safety and Li:ensing staff may provide nuclear
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rafety review as delegated by PRC for:
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a.
Procedures, programs and changes thereto idertified in
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Specification 6.8 and any additional procedures and
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changes thereto identified by the Plar; General Manager
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i as significant to nuclear safety.
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b.
All proposed t ests or experiments.
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c.
All proposed changes or modification.s to plant systC%F
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or equipment.
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d.
The Site Emergency Plan.
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6-9 Amendment No. 75, $5,105,327 TSP 0189-0001-NLO4 l
i f
ADMINISTRATIVE CONTROLS L
1 l
6.5.3.4 AUTHORITY
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1 l
The Plant Safety and Licensing staff shall determine those
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l issues significant to nuclear safety which require review by
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the Plant Review Committee from items considered under
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Specification 6.5.3.3.a through d.
For those items not
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referred to PRC, Plant Safety and Licensing shall recommend
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in writing to plant management approval or disapproval
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of items considered under 6.5.3.3.
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6.5.3.5 RECORDS Reports of Plant Safety and Licensing activities pursuant to
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Specification 6.5.3.3 shall be submitted monthly to PRC.
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6.6 (Deleted) 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 immediately and not restarted until the Commission authorizes resumption of operation (10 CFR 50.36(c)(1)(i)(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 i
NSSD.
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c.
A report shall be prepared in cecordance with 10 CfR 50.36 and 6.9 of this specification.
(The safety limit violation and the report shall be r+ viewed o; The PRC.)
3.
l'he report shall be submitted within 24 days to the Commission (in accordance with ttA requireacato of l
10 CFR 50 3E), to the Vice President - Nuclear Operaticcs and te the NSSD.
I i
l l
1 I
6-10 Amendment No. 37, 75,127 TSP 0189-0001-NLO4
i w.
2 ADMINISTRATIVE CONTROLS-n e
' 6. 8' PROCEDUNES l:
Y 6.8.1 Written procedures shall be established,' implemented' and.
' maintained covering the activities referenced below;
,The applicable procedures recommended in Appendix "A".of a.
Regulatory Guide-1.33 Quality Assurance Program Requirements,'as endorsed by.CPC-2A QAPD.
b.
. Refueling. operations.
- c. ' Surveillance and test activities of safety-related equipment.
1 d.- Site Security Plan implementation.
'e.
Site Emergency Plan implementation.
fs Site Fire Protection Program implementation.
6.8.2 Procedures and' changes shall be approved prior to
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implementation by the appropriate
- senior department manager
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predesignated by the Plant General Manager subject to the
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reviews per Specifications 6.5.1.6 and 6.5.3.
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6.8.3 Temporary changes to procedures of Specification 6.8.1 above.
may be made provided:
a.
The intent of the ceiginal procedure is not altered.
b.' The change is approved by two members (or desi nettd b
alternates) of the PRC, at least one of whom holds a-Senior Reactor Lperator License.
The change is documented, subsequently reviewco by Plant
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c.
Safety and Licensing within 30 days of issuance and
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approved by t'n appropriate
- senior department manager predesi pated by the Plant General Manager.
/
- The determination of the appropriate senior department manager is based on the activities addressed by the specific procedure and will be predesignated in writing by the Plant General Manager.
/
6-10a Amendment No. 37, 75, M3,127
. TSP 0189-0001-NLO4