ML17156A302
| ML17156A302 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 05/28/1985 |
| From: | Butler W Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17156A303 | List: |
| References | |
| NUDOCS 8506060375 | |
| Download: ML17156A302 (18) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 PENNSYLVANIA POWER 5 LIGHT COIIPANY ALLEGHENY ELECTRIC CO PER TIVE, INC.
DOCKET NO. 50-387 SUS UEHANNA STEAN ELECTRIC STATION UNIT 1 ANENDIIENT TO FACILITY OPERATING LICENSE Amendment No.
47 License No. NPF-14 1.
The Nuclear Regulatory Commission (the Commission or the NRC) having found that:
D A.
The application for an amendment filed by the Pennsylvania Power 5 Light Company, dated February ll, 1985 and February 28, 1985 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the ComIission's 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 regulations of the CowIIission; C.
There is reasonable assurance:
(i) that the activities authorized by this amendment can be conducted without endangering the health arId safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter I; 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.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 2.C.(2) of Facility Operating License No. NPF-14 is hereby amended to read as follows:
(2)
Technical S ecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 47, and the Environmental Protection Plan contained in Appendix 8, are hereby incorporated in the license.
PP8L shall operate facility in accordance with the Technical Specifications and the Environmental Protection Plan.
8506060375 850528 PDR ADOCK 05000387 P
3.
This amendment is effective as of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
Attachment:
Chahges to the Technical Specifications Date of Issuance:
NY 8 8 585 Walter R. Butler, Chief Licensing Branch No.
2 Division of Licensing
, ~
re ATTACHMENT TO LICENSE AMENDMENT NO.
FACILITY PER ING LICENSE N
PF-14 DOCKET NO. 50-387 Replace the following pages of the Appendix "A" Technical Specifications with enclosed pages.
the revised pages are identified by Amendment number and contain vertical lines indicating the area of change.
REMOVE 6'-3 6-4.
6-7 6-8 6~11 6-12 INSERT 6-3 6-4 6-7 6-8 6-11 6-12
SEHIOR VICE PRESIOEHT HUCLEAR MANAGER HUCLEAR SAFETY ASSESSMEHT MAHAGER HUCLEAR 9UALITY ASSURANCE MAHAGER - HUCLEAR AOIIIHISTRATION VICE PRESIOEHT NUCLEAR OPERATIONS YICE PRESIOEHT ENGINEERIHG AHO CONSTRUCTIOH HUCLEAR MANAGER NUCLEAR SUPPORT MANAGER NUCL'EAR TRAINING SUPERIHTENOEHT DF PLANT MAHAGER NUCLEAR LICENSIH MANAGER NUCLEAR PLAHT ENGINEER IHG ON SITE Figure 6.2.1-1 OFFSITE ORGANIZATION SUS(UEHANNA " UNIT 1 y ~
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CM tOC Wx SUPER ItiTEtiDENT OF PLANT ASSISTANT SUPERIttTENDEttT I&C SUPERVISOR SUPERVISOR OF OPERATIOtiS SRO SUPERVISOR OF HAItlTENANCE iiEALTH PHYSICS/
CHEHISTRY SUPERVISOR TECIHlICAL SUPERVISOR PERSOtHIEL ADHINISTRATION SUPERVISOR SUPERVISOR OF SECURITY STAFF SHIFT SUPERVISOR SRO STAFF ttADIOLOGICAL PROTECTION SUPVR/STAFF CIIEHISTRY STAFF UNIT I OPERATIOtiS SRO/RO REACTOR ERG ItlEERItiG PLANT ENGItiEERING SHIFT TECHNICAL ADVISOR (D
CL B
iD FIGURE 6.2.2-1 UNIT ORGANIZATION O
AOMINISTRATIVE CONTROLS 6.2.3 NUCLEAR SAFETY ASSESSMENT GROUP (NSAG FUNCTION 6.2.3. 1 The NSAG shall function to examine unit operating characteristics, NRC issuances, industry advisories, Licensee Event Reports, and other sources of plant design and operating experience information, including plants of similar
- design, which may indicate areas for improving plant safety.
COMPOSITION 6.2.3.2 The NSAG shall be composed of at least five dedicated, full-time engineers with at least three located onsite, each with a bachelor's degree in engineering or related science and at least twa years professional level experience in his field, at least one year of which experience shall be in the nuclear field.
RESPONSIBILITIES 6.2.3.3 The NSAG shall be responsible for maintaining surveillance of unit activities to provide independent verification* that these activities are performed correctly and that human errors are reduced as much as practical.
AUTHORITY 6.2.3.4 The NSAG shall make detailed recommendations for revised procedures, equipment modifications, maintenance activities, operations activities, or other means of improving unit safety to the Senior Vice President-Nuclear.
6.2.4 SHIFT TECHNICAL AOVISOR 6.2.4.1 The Shift Technical Advisor shall provide technical support to the Shift Supervisor in the areas of thermal hydraulics, reactor engineering, and plant analysis with regard to the safe operation of the unit.
- 6. 3 UNIT STAFF UALIFICATIONS 6.3. 1 Each member'f the unit staff shall meet or exceed the minimum qualifi-cations of ANSI N18. 1-1971 for comparable positions and the supplemental requirements specified in Section A and C of Enclosure 1 of the March 28, 1980 NRC letter to all licensees, except for the Radiological Protection Supervisor or Health physics/Chemistry Supervisor who shall meet or exceed the qualifica-tions of Regulatory Guide 1.8, September
- 1975, and the shift Technical Advisor who shall meet or exceed the qualifications referred to in Section 2.2. l.b of Enclosure 1 of the October 30, 1979 NRC letter to all operating nuclear power plants.
- 6. 4 TRAINING 6.4.1 A retraining and replacement training program for the unit staff shall b'e maintained under the direction of the Manager - Nuclear Training, shall meet or exceed the requirements and recommendations of Section 5.5 of ANSI N18. 1-1971 and Appendix "A" of 10 CFR Part 55 and the supplemental requirements specified in Section A and C of Enclosure 1 of the March 28, 1980 NRC letter to all licensees, and shall include familiarization with relevant industry operational experience.
~Not responsible for sign-off function.
SUS(UEHANNA " UNIT 1 6-7 Amendment No. 47
ADMINISTRATIVE CONTROLS 6.5 REVIEW AND AUDIT
- 6. 5. 1 PLANT OPERATIONS REVIEW COMMITTEE PORC FUNCTION 6.5.1.1 The PORC shall function to advise the Superintendent of Plant-Susquehanna on matters related to nuclear safety as described in Specification 6.5. 1.6.
COMPOSITION 6.5. 1.2 The PORC shall be composed of the:
Chairman:
Member:
Member:
Member:
Member:
Member:
Member:
Member:
Member:
Superintendent of Plant-Susquehanna Assistant Superintendent of Plant-Susquehanna Supervisor of Operations Technical Supervisor Supervisor of Maintenance I8C/Computer Supervisor Reactor Engineering Supervisor or Unit Reactor Engineer Health Physics/Chemistry Supervisor Shift Supervisor or Unit Supervisor ALTERNATES 6.5. 1.3 All alternate members shall be appointed in writing by the PORC Chairman to serve on a temporary basis;
- however, no,more than two alternates shall participate as voting members in PORC activities at any one time.
MEETING FRE UENCY 6.5. 1.4 The PORC shall meet at least once per calendar month and as convened by the PORC Chairman or his designated alternate.
QUORUM 6.5.1.5 The quorum of the PORC necessary for the performance of the PORC responsibility and authority provisions of these Technical Specifications shall consist of the Chairman'r his designated alternate and four members including alternates.
SUSQUEHANNA - UNIT 1 6"8 Amendment No.47
AOMINISTRATIVE CONTROLS COMPOSITION 6.5.2.2 The SRC shall be composed at least eight, but not more than twelve individuals who shall meet or exceed the requirements of ANSI 3. 1-1981, Sec-tion 4.7.
The Chairman, Vice Chairman and all members shall be appointed in writing by the Senior Vice President-Nuclear.
ALTERNATES 6.5.2.3'll alternate members shall be appointed in writing by the-SRC Chairman to serve on a temporary basis;
- however, no more than two alternates shall participate as voting members in. SRC activities at any one time.
CONSULTANTS
- 6. 5. 2. 4 Consultants shall be utilized as determined by the SRC Chairman to provide expert advice to the SRC.
MEETING FRE UENCY 6.5'.5 The SRC shall meet at least once per calendar quarter during the initial year of unit operation following fuel loading and at least once per six months thereafter.
QUORllM 6.5.2
~ 6 The quorum of the SRC necessary for the performance of the SRC review and audit functions of these Technical Specifications shall consist of not less than a majority of all members, or designated alternates, and shall be subject to the following constraints:
the Chairman or his designated alternate shall be present for all formal meetings; and no more than a minority of the quorum shall have line responsibility for operation of the unit.
REVIEW 6.5.2.7 The SRC shall be responsible for the review of:
The safety evaluations for 1) changes to procedures, equipment or systems and 2) tests or experiments completed under the provision of 10 CFR 50.59 to verify that such actions did not constitute an unreviewed safety question.
b.
C.
Proposed changes to procedures, equipment or systems which involve an unreviewed safety question as defined in 10 CFR 50.59.
Proposed tests or experiments which involve an unreviewed safety question as defined in 10 CFR 50.59.
SUS(UEHANNA - UNIT 1 6-11 Amendment No. 47
ADMINISTRATIVE CONTROLS REVIEW (Continued) d.
e.
Proposed changes to Appendix A Technical Specifications or this Operating License.
Violations of codes, regulations,
- orders, Technical Specifications, license requirements, or of internal procedures or instructions having nuclear safety significance.
Significant operating abnormalities or deviations from normal and expected performance of unit equipment that affect nuclear safety.
All REPORTABLE EVENTS.
All recognized indications of an unanticipated deficiency in some aspect of design or operation of structures,
- systems, or components that could affect nuclear safety.
Reports and meetings minutes of the PORC.
AUDITS 6.5.2e8 Audits of unit activities. shall be performed under the cognizance of the SRC.
These audits shall encompass:
The conformance of unit operation to provisions contained within the Appendix A Technical Specifications and applicable license conditions at least once per 12 months.
b.
The performance, training and qualifications of the entire unit staff at least once per 12 months.
C.
The results of actions taken to correct deficiencies occurring in unit equipment, structures, systems or method of operation that affect nuclear safety at least once per 6 months.
d.
The performance of activities required by the Operational guality Assurance Program to meet the criteria of Appendix "B", 10 CFR 50, at least once per 24 months.
The Emergency Plan and implementing procedures at least once per 12 months.
The Security Plan and implementing procedures at least once per 12 months.
Any other area of unit operation considered appropriate by the SRC or the Senior Vice President-Nuclear.
h.
The Fire Protection Program and implementing procedures at least once per 24 months.
SUS(UEHANNA - UNIT 1 6-12 Amendment No. j9
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UNITEDSTATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 PENNSYLVANIA POWER 5 LIGHT COMPANY ALLEGHENY ELECTRIC COOPERATIVE INC.
DOCKET NO. 50-388 SUS UEHANNA STEAM ELECTRIC STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 12 License No. NPF-22 1.
The Nuclear Regulatory Commission (the Commission or the NRC) having found that:
A.
The application for an amendment filed by the Pennsylvania Power
& Light Company, dated February 11, 1985 and February 28, 1985 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's 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 regulations of the Corrmission; 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 Commission's re'gulations set forth
. in 10 CFR Chapter I; 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.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 2.C.(2) of Facility Operating License No. NPF-22 is hereby amended to read as follows:
(2)
Technical S ecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 'l2, and the Environmental Protection Plan contained in Appendix 8', are hereby incorporated in the license.
PP8L shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This amendment is effective as of the date of issuance.
FOR TME NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications Date of Issuance: "
~ 8 Ma1ter R. But1er, Chief Licensing Branch No.
2 Division of Licensing
ATTACHMENT TO LICENSE AMENDMENT NO.
12 F CILITY P
R TING LICENSE NO. NPF-22 DOCKET. NO. 50-388 Replace the following pages of the Appendix "A" Technical Specifications with enclosed pages.
the revised pages are identified by Amendment number and contain vertical lines indicating the area of change.
REMOVE 6-3 6-4 6-7 6-8 INSERT 6-3 6-4 6-7 6-8 6-11 6-12
SENIOR VICE tRESIOEHT HUCLElR RLNACER NUCLEAR SLFETT ASSESSMENT HAKACKR NUCLEAR OUALITT ASSURANCE NAHACER - NUCLEAR lORIHISTRATIOH TICE FRESIOEHT NUCLEAR OPERATIONS TICE PRKSIOEHT ENCINEERIHC ANO COHSTRUCTIOH NUCLEAR RANACKR NUCLEAR SUFFORT RANACER NUCLEAR TRAINIKC SUPERIHTKHOEHT OF FLAKE XAKACER KUCLEAR LICEKSIK HAHACER KUCLKAR FLANK ENCIHEERIHC OH SITE FIGURE 6.2.1-1 OFFSITE ORGANIZATION
SUPERINTEtlDEtlT OF PLAttT ASSISTANT SUPERINTENDENT It'C SUPERVISOR SUPERVISOR OF OPERATIONS SRO SUPERVISOR OF NAIHTEtlhHCE HEALTH PHYSICS/
CIIENISTRY SUPERVISOR TECHNICAL SUPERVISOR PERSONNEL 6 ADNIHISTRATIOH SUPERVISOR SUPERVISOR OF SECURITY Sl IIFT SUPERVISOR SRO STAFF RADIOLOGICAL PROTECTION SUPVR/STAFF CHENISTRY STAFF UNIT I OPERATIOtlS SRO/RO REACTOR EHGINEERItlG PLAttT EtlGIHEERING SHIFT TECHNICAL ADVISOR FIGURE 6.2.2-1 UNIT ORGANIZATION
ADMINISTRATIVE CONTROLS 6.2.3 NUCLEAR SAFETY ASSESSMENT GROUP (NSAG FUNCTION 6.2.3. 1 The NSAG shall function to examine unit operating characteristics, NRC issuances, industry advisories, Licensee Event Reports, and other sources of plant design and operating experience information, including plants of similar
- design, which may indicate areas for improving plant safety.
COMPOSITION
- 6. 2. 3. 2 The NSAG shall be composed of at least five dedicated, full-time engineers with at least three located onsite, each with a bachelor's degree in engineering or related science and at least two years professional level experience in his field, at least one year of which experience shall be in the nuclear field.
RESPONSIBILITIES 6.2.3.3 The NSAG shall be responsible for maintaining surveillance of unit activities to provide independent verification" that these activities are performed correctly and that human errors are reduced as much as practical.
'UTHORITY 6.2.3.4 The NSAG shall make detailed recommendations for revised procedures, equipment modifications, maintenance activities, operations activities, or other means of improving unit safety to the Senior Vice President-Nuclear.
- 6. 2. 4 SHIFT TECHNICAL ADVISOR 6.2.4.1 The Shift Technical Advisor shall provide technical support to the Shift Supervisor in the areas of thermal hydraulics, reactor engineering, and plant analysis with regard to the safe operation of the unit.
- 6. 3 UNIT STAFF UALIFICATIONS 6.3.1 Each member of the unit staff shall meet or exceed the minimum qualifica-tions of ANSI N18.1-1971 for comparable positions and the supplemental require-ments specified in Sections A and C of Enclosure 1 of the March 28, 1980 NRC letter to all licensees, except for the Radiological Protection Supervisor or Health Physics/Chemistry Supervisor who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975,. and the Shift Technical Advisor who shall meet or exceed the qualifications referred to in Section 2.2. l.b of Enclosure 1 of the October 30, 1979 NRC letter to all operating nuclear power plants.
- 6. 4 TRAINING 6.4.1 A retraining and replacement training program for the unit staff shall be maintained under the direction of the Manager - Nuclear Training, shall meet or exceed the requirements and recommendations of Section 5.5 of ANSI N18. 1-1971 and Appendix A of 10 CFR Part 55 and the supplemental requirements specified in Sections A and C of Enclosure 1 of the March 28, 1980 NRC letter to all licensees,
.and shall include familiarization with relevant industry operational experience.
- Not responsible for sign-off function.
SUS(UEHANNA - UNIT 2 6-7 Amendment No. 12
ADMINISTRATIVE CONTROLS
- 6. 5 REVIEW AND AUDIT
- 6. 5. 1 PLANT OPERATIONS REVIEW COMMITTEE PORC FUNCTION 6.5. 1. 1 The PORC shall function to advise the Superintendent of Plant-Susquehanna on matters related to nuclear safety as described in Specification
- 6. 5. 1. 6.
COMPOSITION 6.5. 1.2 The PORC shall be composed of the:
Chairman:
Member:
Member:
Member:
Member:
Member:
Member:
Member:
Member:
Superintendent of Plant.-Susquehanna Assistant Superintendent of Plant-Susquehanna Supervisor of Operations Technical Supervisor Supervisor of Maintenance I8C/Computer Supervisor Reactor Engineering Supervisor or Unit Reactor Engineer Health Physics/Chemistry Supervisor Shift Supervisor or Unit Supervisor ALTERNATES
- 6. 5. 1. 3 All alternate members shall be appointed in writing by the PORC Chairman to serve on a temporary basis;
- however, no more than two alternates shall participate as voting members in PORC activities at any one time.
MEETING FRE UENCY 6.5. 1.4 The PORC shall meet at least once per calendar month and as convened by the PORC Chairman or his designated alternate.
UORUM 6.5.1.5 The quorum of the PORC necessary for the performance of the PORC responsibility and authority provisions of these Technical Specifications shall consist of the Chairman or his designated alternate and four members including alternates.
SUSQUEHANNA " UNIT 2 6"8 Amendment No. 12
EE 4
ADMINISTRATIVE CONTROLS COMPOSITION 6.5;2.2 The SRC shall be composed of at least eight, but no more than twelve individuals who shall meet or exceed the requirements of ANSI 3. 1-1981, Sec-tion 4.7.
The Chairman, Vice Chairman and all members shall be appointed in writing by the. Senior Vice President-Nuclear.
ALTERNATES 6.5.2.3 All alternate members shall be appointed in writing by the SRC Chairman to serve on a temporary basis;
- however, no more than two alternates shall participate as voting members in SRC activities at any one time.
CONSULTANTS 6.5.2.4 Consultants shall be utilized as determined by the SRC Chairman to provide expert advice to the SRC.
~EETI% FREIEE Y
1) 6.5.2.5 The SRC shall meet at least once per calendar quarter during the initial year of unit operation following fuel loading and at least once per 6 months thereafter.
gUORUM 6.5.2.6 The quorum of the SRC necessary for the performance of the SRC review and audit functions of these Technical Specifications sh'all consist of not less than a majority of all members, or designated alternates, and shall be subject to the following 'constraints:
the Chairman or his designated alternate shall be present for all formal meetings:
and no more than a minority of the quorum shall have.line responsibility for operation of the unit.
REVIEW 6.5.2.7 The SRC shall be responsible for the review of:
a.
b.
. 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 did not constitute an unreviewed safety question.
Proposed changes to procedures, equipment or systems which involve an unreviewed safety question as defined in 10 CFR 50.59.
Proposed tests or experiments which. involve an unreviewed safety question as defined in 10 CFR 50.59.
SUSQUEHANNA.- UNIT 2 6-11 Amendment No. 12
ADMINISTRATIVE CONTROLS REVIEW (Continued) d.
e.
g.
h.
Proposed changes to Appendix A Technical Specifications or this Operating License.
Violations of codes, regulations,
- orders, Technical Specifications,
.license requirements, or of internal procedures or instructions having nuclear safety significance.
Significant operating abnormalities or deviations from normal and expected performance of unit equipment that affect nuclear safety.
All REPORTABLE EVENTS.
All recognized indications of an unanticipated deficiency in some aspect of design or operation of structures,
- systems, or components that could affect nuclear safety.
AUOITS Reports and meetings minutes of the PORC.
6.5.2e8 Audits of unit activities shall be performed under the cognizance of the SRC.
These audits shall encompass:
a ~
b.
C.
d.
The conformance of unit operation to provisions contained within the Appendix A Technical Specifications and applicable license conditions at least once per 12 months.
The performance, training and qualifications'of the entire unit staff at least once per 12 months.
The results of actions taken to correct deficiencies occurring in unit equipment, structures, systems or method of operation that affect nuclear safety at least once per 6 months.
The performance of activities required by the Operational guality Assurance Program to meet the criteria of Appendix B, 10 CFR Part 50, at least once per 24 months.
e.
The Emergency Plan and implementing procedures at least once per 12 months.
The Security Plan and implementing procedures at least once per 12 months.
Any other area of unit operation considered appropriate by the SRC or the Senior Vice President-Nuclear.
h.
The Fire Protection Program and implementing procedures at least once per 24 months.
SUS(UEHANNA - UNIT 2 6-12