ML20077F083
| ML20077F083 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 07/19/1983 |
| From: | Clark R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20077F087 | List: |
| References | |
| NUDOCS 8308010044 | |
| Download: ML20077F083 (20) | |
Text
'c UNITED STATES y' " ' p ( h NUCLEAR REGULATORY COMMISSION
'E WASHINGTON, D. C. 20555
- \\/
BALTIMORE GAS AND ELECTRIC COMPANY DOCKET NO. 50-317 CALVERT CLIFFS NUCLEAR POWER PLANT UNIT NO~. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 85 License No. DPR-53 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Baltimore Gas & Electric Company (the licensee) dated April 27, 1983, 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 gthe Commission; 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 condected in compliance with the Commission'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 i
requirements have been satisfied.
O
-,C 8308010044 830719 PDR ADOCK 05000317 P
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< 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. DPR-53 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 85, 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 the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
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Robert A. Clark, Chief Operating Reactors Branch #3 Division of Licensing i
Attachment:
Changes to the Technical Specifications Date of Issuance: July 19, 1933 M
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ATTACHMENT TO LICENSE AMENDMENT NO. 85 FACILITY OPERATING LICENSE N0. DPR-53 DOCKET NO. 50-317 Replace the following pages of the Appendix A Technical Specifications
]
with the enclosed pages as_ indicated. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change. The corresponding overleaf pages are also provided to maintain i
document completeness.
Pages 3/4 7-31 3/4 7-63 3/4 7-64 6-3 6-6 i
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h TABLE 3.7-4 3
SAFETY RELATED HYDRAULIC SNUBBERS
- P M
SNUBBER SYSTEM SNUBBER INSTALLED ACCESSIBLE OR llIGH RADIATION ESPECIALLY DIFFICULT E
N0.
ON, LOCATION AND ELEVATION INACCESSIBLE ZONE **
TO REMOVE h
{A or 1)
-(Yes or No)
(Yes or Yo)~~~ " ~
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l-36-1 SUCTION #11 AUX. FEED PUMP 12' A
No rio 1-36-1A SUCTION #11 AUX. FEED PUMP 12' A
No '
No w1 u
(
l-38-5 PRESSURIZER SAMPLE LIllES 24' I
Yes No y
1-38-6 PRESSURIZER SAMPLE LINES 37' I
Yes No g-1-24-1 DIESEL GENERATOR #12 EXHAUST 92' A
No No E"
1-24-2 DIESEL GENERATOR #11 EXHAUST 92' A
No No E
3
TABLE 3.7-4 g
SAFETY RELATED flYDRAULIC SNUBBERS
ON, LOCATION AND ELEVATION INACCESSIBLE ZONE **
TO REMOVE p
(A or I)
(Yes or No)
(Yes or No) 1-24-3 EMERGENCY DIESEL #12 EXHAUST 61' A
No No 1-24-3A EMERGENCY DIESEL #12 EXilAUST 61' A
No No 1-24-4 EMERGENCY DIESEL #11 EXilAUST 61' A
No i
No 1-24-4A EMERGENCY DIESEL #11 EXilAUST 61' A
No No D'ESEl GENERATOR #21 EXHAUST 92' A
No No 1-24-5 I
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{
1-24-6 DIESEL GENERATOR #21 EXilAUST 62' A
No No
?
l-24-6A DIESEL GENERATOR #21 EXilAUST 62' A
No No M
1-28-1 UNIT 1 AFW PUMP ROOM 22' A
No No 1-28-2 UNIT 1 AFW PUMP ROOM 22' A
No No 1-28-3 UNIT 1 AFW PUMP ROOM 22' A
No No p
E.
1-41-1 '
SUCTION #13 CHARGING PUMP -10' A
No No 5
l-41-2 AUX. SPRAY 65' I
Yes No Y
l-41-3 AUX. SPRAY 65' I
Yes No 0
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PLANT SYSTEMS 3/4.7.9 SEALED SOURCE CONTAMINATION LIMITING CONDITION FOR OPERATION 3.7.9.1 Each sealed source containing radioactive material either in excess of 100 microcuries of beta and/or gamma emitting material or 5 microcuries of alpha emitting material shall be free of > 0.005 microcuries of removable contamination.
APPLICABILITY: At all times.
ACTION:
a.
Each sealed source with removable contamination in excess of the above limit shall be immediately withdrawn from use and:
1.
Either decontaminated and repaired, or 2.
Disposed of in accordance with Commission Regulations.
b.
The provisions of Specifications 3.0.3 and 3.0.4 are not appli-cable.
6 SURVEILLANCE REQUIREMENTS 4.7.9.1.1 Test Requirements - Each sealed source shall be tested for leakage and/or contamination by:
a.
The licensee, or b.
Other persons specifically authorized by the Commission or an Agreement State.
The test method shall have a detection sensitivity of at least 0.005 microcuries per test sample.
4.7.9.1.2 Test Frequencies - Each category of. sealed sources (excluding startup sources and fission detectors previously subjected to core flux) shall be tested at the frequencies described below.
Sources in use - At least once per six month's 'for all sealed a.
sources containing radioactive material:
CALVERT CLIFF 5
'JNIT 1 3/4 7-63 Amendment No. 05
l PLANT SYSTEMS t
SURVEILLANCE REQUIREMENTS (Continued) 1.
With a half-life greater than 30 days (excluding Hydrogen 3),and 2.
In any form other than gas.
b.
Stored sources not in use - Each sealed source and fission detector shall be tested prior to use or transfer to another licensee unless tested within the previous six months.
Sealed sources transferred without a certificate indicating the last test date shall be tested prior to being placed into use.
c.
Startup sources and fission detectors - Each sealed startup source and fission detector shall be tested within 31 days prior to being subjected to core flux or installed in the core and following repair or maintenance to the source or detector.
4.7.9.1.3 Reports - A report shall be prepared and submitted to the Commission on an annual basis if sealed source or fission detector leakage tests reveal the_ presence of > 0.005 microcuries of removable contam nation.
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W CALVERT CLIFFS-UNIT 1 3/4 7-64 Amendment No. 85
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R0 - Reactor Operator License Co""o' SR0 - Senior Reactor Operator Rrxim Op.ai.
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Figure 6.2.2 Organization Chart (Two Unit Operation) - Calvert Cliffs Nuclear Power Plant
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Balti:aore Gas and Electric Company w
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l TABLE 6.2-1 MINIMUM SHIFT CREW COMPOSITION #
Condition of Unit 1 - Unit 2 in MODES 1, 2, 3 or 4 APPLICABLE MODES LICENSE CATEGORY 1, 2, 3 & 4 5&6 SOL **
2 2*
OL**
3 3
l 6Non-Licensed 3
3 Shift Technical Adviscr if#
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Condition of Unit 1 - Unit 2 in MODES 5 or 6 LICENSE APPLICABLE MODES CATEGORY 1, 2, 3 & 4 5&6 S0L**
2 1*
OL**
3 2
Non-Licensed 3
3 Shift Technical Advisor l##
0 CALVERT CLIFFS - UNIT 1-Amendment No. f/J,gg L.
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j TABLE 6.2-1 (Continued) t 4
- Does not include the licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handling, supervising CORE ALTERATIONS during fuel reloading.
l
- Assumes each individual is licensed on each unit.
2 j
- Shift crew composition _may be less than the minimum requirements for a j
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 orde*r to accommodate unexpected absence of on duty shift crew members provided immediate action is taken to restore the shift crew composition to within the minimum requirements of Table 6.2.1.
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must be an SOL holder in addition to the one SOL required.
With both units in MODE 1, 2, 3 or 4, the STA must be an SOL holder in addition to the two SOL's required.
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CALVERT CLIFFS - UNIT 1 Amendment No. 53 1
6-5 4
e ADMINISTRATIVE CONTROLS 6.3 FACILITY STAFF QUALIFICATIONS 6.3.1 Each member of the facility staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions, except for the Radiation Safety Engineer 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 General Supervisor - Training and Technical Services for the Nuclear Power Department and the General Foreman for the Production Maintenance Department and 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, as applicable.
6.4.2 A training program for the Fire Brigade shall be maintained under the direction of the General Supervisor - Training and Technical Services and shall meet or exceed the requirements of Section 27 of the NFPA Code-1975.
6.5 REVIEW AND AUDIT 6.5.l' PLANT OPERATIONS AND SAFETY REVIEW COMMITTEE (POSRC)
FUNCTION 6.5.1.1 The POSRC shall function to advise the Plant Superintendent-on all matters related to nuclear safety.
CGMPOSITION 6.5.1.2 The POSRC shall be composed of the:
Chairman:
Plant Superintendent Member:
General Supervisor - Operations Member:
General Supervisor - Electrical and Controls Member:
General Supervisor - Chemistry l
Member:
Principal Engineer - Plant Engineering Nuclear Member:
General Supervisor - Maintenance and Nodifications i
Member:
Pr,incipal Engineer - Incore Fuel Management
(
Member:
General Supervisor - Radiation Safety
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Member:
General Supervisor - Training and Technical Services ALTERNATES
- 6. 5.'l. 3 All alternate members-shall be appointed in writing by the POSRC Chairman to serve on a temporary basis; however, no more than two alternates shall participate as voting members in POSRC activities at any one time.
CALVERT CLIFFS - UNIT 1 6-6 Amendment No,'26, A3, 5), AII/ 85
/pa ucy'o UNITED STATES 8 \\ '),. '
NUCLEAR REGULATORY COMMISSION p
WASH!NGTON, D C. 20555 wf BALTIMORE GAS AND ELECTRIC COMPANY DOCKET N0.~ 50-318 CALVERT CLIFFS NUCLEAR POWER PLANT UNIT N0.~2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 68 License No. DPR-69 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Baltimore Gas & Electric Company (the licensee) dated April 27, 1983, 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 I tne Commission; C.
There is reasonable asturance (i) that the activities authorizea by this acen.iment can be conducted without 1
endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regJlatinPS; D.
The issuance of this amer.dment will not be inimical to the common dafense and security or to the health and safety of tne 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.
t S
l
- 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. DPR-69 is hereby amended to read as follows:
2 Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 68, 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 the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION f
Y Robert A. Clark, Chief Operating Reactors Branch #3 Division of Licensing i
Attachment.
Changes to the Technical Specifications Date of Issuance: July 19, 1983 en a
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ATTACHMENT TO LICENSE AMENDMENT NO. 68 FACILITY OPERATING LICENSE NO. DPR-69
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DOCKET NO. 50-318 I
Replace the following pages of the Appendix A Technical Specifications with the enclosed pages as indicated. The revised pages are identified by Amendment number and contain vertical lines' indicating the area of change. The corresponding overleaf pages are also provided to maintain document completeness.
,Pages 3/4 7-55 3/4 7-56 6-3 6-6 6
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PLANT SYSTEMS 3/4.7.9 SEALED SOURCE CONTAMINATION LIMITING CONDITION FOR OPERATION 3.7.9.1 Each sealed source containing radioactive material either in excess of 100 microcuries of beta.and/or gamma emitting material or 5 microcuries of alpha emitting material shall be free of > 0.005 microcuries of removable contamination.
APPLICABILITY: At all times.
ACTION:
a.
Each sealed source with removable contamination in excess of the above limit shall be immediately withdrawn from use and:
1.
Either decontaminated and repaired, or 2.
Disposed of in accordance with Commission Regulations.
b.
The provisions of Specifications 3.0.3 and 3.0.4 are not appli-cable.
I SURVEILLANCE REQUIREMENTS
'4.7.9.1.1 Test Requirements - Each sealed source shall be tested for leakage and/or contamination by:
a.
The licensee, or b.
Other persons specifically authorized by the Commission or an Agreement State.
The test method shall have a detection sensitivity of at least 0.005 j-microcuries per test sample.
4.7.9.1.2 Test Frequencies - Each~ category of sealed sources (excluding
~
lstartup sources and fission detectors previ.ously subjected to core flux) i
.shall be tested at the frequencies described below.
a.
Sources in use - At least once-per six months for. all sealed sources containing radioactive material:
l CALVERT CLIFFS - UNIT 2 3/4 7-55 Amendment. No. 68
+
-g.
r PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) 1.
With a half-life greater than 30 days (excluding Hydrogen 3),and 2.
In any form other than gas. ',
b.
Stored sources not in use - Each sealed source and fission detector shall be tested prior to use or transfer to another licensee unless tested within the previous six months.
Sealed sources transferred without a certificate indicating the last test date shall be tested prior to being placed into use.
c.
Startup sources and fission detectors - Each sealed startup source and fission detector shall be tested within 31 days prior to being subjected to core flux or installed in the core and following repair or maintenance to the source or detector.
4.7.9.1.3 Reports - A report shall be prepared and submitted to the Commission on an annual basis if sealed source or fission detector i
leakage tests reveal the presence of > 0.005 microcuries of removable contamination.
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l CALVERT CLIFFS-UNIT 2 3/4 7-56 Amendment No. 68
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Sec"nty Safety Support GrouD Operatens Ominstry h'""""9 I "'""""E U""h4 6 Controls Norlear M W rmumt Nimicar Assurance u
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TABLE 6.2-1 MINIMUM SHIFT CREW COMPOSITION #
l Condition of Unit 2 - Unit 1 in MODES 1, 2, 3 or 4 APPLICABLE MODES LICENSE CATEGORY l, 2, 3 & 4 5&6 50L**
2 2*
OL**
3 3
l on-Licer4cd 3
3 i
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Condition of Unit 2 - Uni,t 1 in MODES 5 or 6 I
~
LICENSE APPLICABLE MODES CATEGORY 1, 2, 3 & 4 5&6 SQL**
2 1*
OL**
3 2
l Non-Licensed 3
3 Shift Technical Advisor l##
0 CALVERT. CLIFFS
. UNIT 2 6-4 Amendment No. ' 36, 3 0
TABLE 6.2-1 (Continued)
- Does not include the licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handling, supervising CORE ALTERATIONS during fuel reloading.
- Assumes each individual is licensed on each unit.
- Shift crew composition may be less than the minimum requirements for a period of time not to erteed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order'to accommodate unexpected absence of on duty shif t crew members provided immediate action is taken to restore the shif t crew composition to within the minimum requirements of Tabl e 6.2.1.
With both units in MODE 1, 2, 3 or 4, the STA must be an SOL holder in addition to the two SOLs required.
6 l
l CALVERT CLIFFS - UNIT 2 6-5 Amendment No. 36 l
ADMINISTRATIVE CONTROLS 6.3 FACILITY STAFF OUALIFICATIONS 6.3.1 Each member of the facility staff shall meet or exceed the minimum qualifica-tions of ANSI N18.1-1971 for comparable positions, except for the Radiation Safety Engineer 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 a'nalysis 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 General Supervisor - Training and Technical Services for the Nuclear Power Department and the General Foreman for the Production Maintenance Department and 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, as applicable.
6.4.2 A training program for the Fire Brigade shall be maintained under the direction of the General Supervisor - Training and Technical Services and shall meet or exceed the requirements of Section 27 of the NFPA Code-1975.
6.5 REVIEW AND AUDIT 6.5.1 PLANT OPERATIONS AND SAFETY REVIEW COMMITTEE (POSRC)
FU'iCTION 6.5.1.1 The POSRC shall function to advise the Plant Superintendent on all matters related to nuclear safety. -
COMPOSITION
'l
'6.5.1.2 The POSRC shall be ccmposed of +.ha:
Chairman:
Plant Superintendent Member:
General Supervisor - Operations Member:
General Supervisor - Electrical and ContFols Member:
General Supervisor - Chemistry Member:
Principal Engineer - Plant Engineering Nuclear Member:
General Supervisor - Maintenance and Modifications "1 Member:
Pr.incipal Engineer - Incore Fuel Management
~
~ i Member:
General Supervisor - Radiation Safety Member:
General Supervisor - Training and Technical Services ALTERNATES 6.5.1.3 All alternate members shall be appointed in writing by the POSRC Chairman to serve on a tenporary basis; however, no more than two alternates shall participate as voting members in POSRC activities at any one time.
CALVERT CLIFFS - UNIT 2 6-6 Amendment No. 77, 26, 36, (Ak,68