ML20065P988
| ML20065P988 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 12/12/1990 |
| From: | CAROLINA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML20065P984 | List: |
| References | |
| GL-88-01, GL-88-1, NUDOCS 9012140169 | |
| Download: ML20065P988 (13) | |
Text
{{#Wiki_filter:_ _ _ _ _ _ _ . _ _ _ _ _ . . . _ _ . _ _ _ . , _ _ . . . . . ___m.. .__ . _ . . . - . . _ _ . _ . _. . . _ . .. J , s ENCIDSUB1 1 l , BRUNSWICK STEAM ELECTRI.; PIANT, UNITS 1 AND 2 NRC DOCKETS ,*J.325 6 50 324 i OPERATING LICENSES DPR 71 & DPR.62 i REQUEST TOR LICENSE AMENDMENT ICSCC REQUIREMENTS TECHNICAL SPECIFICATIONS PAGES . UNIT 1 1 2 i s i 9012140169 901212 n PDR ADOCK 05000324 PDC P . . . . . . - . : . .. . . - _ . ~ . - . . - . - . - - - . - . .. - . ,.. . . . . - . . - , . . - . _ - . , . , .. -. . . . . .
i , APPLICABILITY SURVEILLANCE REQUIREMENTS 4.0.1 Surveillance Requirements shall be applicable during the OPERATIONAL CONDITIONS or other states specified f or individual Limiting Conditions for Operation unless otherwise stated in an individual Surveillance Requirement. 4.0.2 Each Surveillance Requirement shall be performed within the specified time interval with a maximum allowable extensior. not to exceed 25% of the a surveillance interval. 4.0.3 Per f ormance of a Surveilla nce Requirement within the specified time interval shall constitute compliaice with OPERABILITY requirements for a Limiting Condition f or Opera'. ion aid associated ACTION statement s unless e otherwise required by the specification. Surveillance requirements do not have to be performed on inoperable equipment. 4.0.4 Ent ry into an OPERATIONAL CONDITION or other specified applicable state shall not be made unless the Surveillanet Requirement (s) associated with the Limiting Condition f or Operation have beto performed within the applicable surveillance interval or as otherwise specified. 4.0.5 Surveillance Requirements for inservice inspection and testing of ASME Cods Class 1, 2, and 3 component s shall be applicable as f ollows
- a. Inservice inspection of ASME Code Class 1, 2, and 3 components and inservice testing of ASME Code Class 1, 2, and 3 pumps and valves shall be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10 CFR 50 Section 50.55s(g), except where specific written relief has been granted by the Commission pursuant to 10 CFR 50, Section 50.55a(s) (6)
(i). BRUNSWICK - UNIT 1 3/4 0-2 Amendment No. v*e,- w '- y -4
' u- w -'- - +- ---w - e-.e ,,e te, q w, -r-9-ww-+: -g- 1r--'N'rr i :Pr F <*--5
e t 3/4.0 APPLICABILITY SURVEILLANCE REQUIREMENTS (Continued)
- b. Surveillance intervals specified in Section XI of the ASME Boiler and Pressure Vessel. Code and applicable Addenda for the inservice inspection and testing activities required by the ASME Boiler and Pressure Vessel Code and applicable Addenda shall be applicable as follows in these Technical Specifications 7 ASME Boiler and Pressure Vessel Required frequencies Code and applicable Addenda for performing inservice termino;vgv for inservice inspection and testing inspect ion ni.4 t esting act ivit ies activities Weekly At least once per 7 days Monthly At least once per 31 days Quarterly or every 3 months At least once per 92 days Semiannually or every 6 months At least once per 184 days Yearly cr annually At least once per 366 days
- c. The provisions of Specification 4.0.2 are applicable to the above required frequencies for performing inservice inspection and testing activities.
- d. Performance of the above inservice inspection and testing activities shall be in addition to other specified Surveillance Requirements.
- c. Nothing in the ASME Boiler and Pressure Vessel Code shall be construed to supersede the requirements of anv t echnical Specification.
- f. The Inservice inspection Program for piping Identified in NRC Ceneric Letter 88-01 shall be performed in accordance with the staf f positions on schedule, methods & personnel & sample expansion inicuded in this lette.
BRUNSWICK - UNIT 1 3/4 0-3 Amendment No.
_ _ , . _ _ - _ _ _ . - _ _ . _ _ _ . _ .__ ____ ___.__._____m .. _ , _ _ i REACTOR COOL.*NT SYSTEM OPERATIONAL LEAK %CE
- LiMITQC Cord,M10N FOR OPERATION 3.4.3.2 Reactor coolant system leakage shall be limited t ot
- a. No PRESSURE BOUNDARY LEAKACE.
- b. $ gpm UNIDENTir!ED LEAKAGE averaged over any 24-hour period.
i
- c. 25 gpm total leakage averaged over any 24-hour period.
- d. 2 gpm increase in UNIDENTIFIED LEAKAGE wit hin any 24-hour period except for the first 24 hours of react or start up commencing with ent ry into OPERATIONAL CONDITION 2.
APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, and 3. ACTION
- a. With any PRESSURE BOUNDARY LEAKACE, be in at least il0T SHUTDOWN within 12 hours and in COLD SilDTDOWN within the next 24 hours.
- b. With any reactor. coolant system leakage greater than any one of the above limits, excluding PRESSURE BOUNDARY LEAKAGE, reduce the leakage rate to within the limits within 8 hours or be in at least il0T SliUTDOWN within the next 12 hours and in COLD SliUTIOWN wit hin the following 24 hours.
SURVElLLANCE REQUIREMENTS 4.4.3.2 The reactor coolant system leakage shall be demonst rated to be within each of the above-limits byt
.a. Monitoring the drywell and equipment drain sump flow rates at least once per B hours, and
- b. Monitoring the primary containment atmosphere particulate and gaseous radioactivity at least once per 24 hours.
BRUNSWICK - UNIT 1 3/4 4-6 Amendment No.
l l APPLICABILITY BASES 4.0.5 This spec'fication ensures that inservice inspection of ASME Code Class 1, 2, and 3 comlonent s and inservice _ testing of ASME Code Class 1, 2, and 3 pumps and valves will be performed in accordance with a periodically updated version of Section XI of the ASME Boiler and Pressure Vessel Code and Addenda as required by 10 CFR $0, Section 50.55a. Relief from any of the above requirements has been provided in writing by the Commission and is not a part of these technical specifications. This specification includes a clarification of the frequencies for performing the inservice inspection and testing activities required by Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda. This clarification is provided to ensure consistency in surveillance intervals throughout these Technical Specifications and to remove any ambiguities relative to the frequencies for performing the required inservice inspection and testing activities. Under the terms of this specification, the more restrictive requirements of the Technical Specifications take precedence over the ASME Boiler and Pressure Vessel Code and applicable Addenda. For example, t he requirement s of Specification 4.0.4 to perform surveillance activities prior to entry into an OPERATIONAL MODE or other specified applicability condition takes precedence over the ASHE iloiler and Pressure Vessel Code provision which allows pumps to be tested up to one week af ter return to normal operation. And, for example, the Technical Specification definition of OPERABLC does not grant a grace period before a device that is not capable of performing its specified f unction is ueclared inoperable and takes prei Jence over the ASME Boiler and Pressure' Vessel Code provision which allows a <alve to be incapable of performing its specified f unction for up to 24 hours bef ore being declared inoperable. This specification includes a statement that the inservice inspection Program for pipe covered by the scope of CL 88-01 will be in conf ormance with the stat f positions on schedule, methods and personnel, and sample expansion included in CL 88-01. This requirement may be removed form the technical specifications in the future in line with the. Technical Specification improvement programs, n-l BRUNSWICK - UNIT 1 B 3/4 0-3 Amendment No.
i 3 REAC1DR COOLANT SYSTEM BASES _ These specifications are based on the guidance of Ceneral Electric S!L #380, Rev. 1, 2-10-84 3/4.4.2 SAFETY /REl.lEP_ VALVES The reactor coolant system saf et y valve f unct ion of the safety-relief valves. operate to prevent the system f rom being pressurit.ed above the Saf ety Limit of 1325 psig. The system is designed to meet the requirements of the ASME Boiler and Pressure Vessel Code Section !!! f or the pressure vessel and ANSI B31.1, 1975, Code for the reactor coolant system piping. 3/4.4.3 REACTOR COOLANT SYSTEM LEAKACE 3/4.4.3.1 L
'EAKACE DETECTION SYSTEMS The RCS leakage detection systems required by this specification are provided t o monitor and detect leakage f rom the Reactor Coolant Pressure boundary. These detection systems are consistent with t he recommendat ions of Regulatory Guide 1.45, " Reactor Coolant Pressure Boundary Leakage Det ect ion Systems." -
3/4.4.3.2 OPERATIONAL LEAKAGE Th e allowable leakage rates of coolant from the reactor coolant system have been base) on the predicted and experimentally observed behavior of cracks in pipes.- The normally expected background leakage due to equipment design and the detection capability of the instrumentation for determining syst em leakage was also considered. The evidence 'obtained f rom experiments suggests that f or leakage somewhat greater than that specified f or unidentified leakage, the probability is small that the imperf ect ion or crack associated with_ such leakage would grow rapidly. However, in all cases, if the leakage rates exceed the values specified or the leakage is located and known to be PRESSURE BOUNDARY LEAKACE, the r tactor will be shut down t o allow further investigation and corrective actic.. Monitoring leakage at eight hour intervals is in conformance with the 12/21/89 NRC SER for CL 88-01. 3/4.4.4 CHEMISTRY The reactor water chemistry limits are established to prevent dama ge to the reactor materials in contact with the coolant. Chloride limits are specified to prevent stress corrosion cracking of the stainless steel. The etfeet of chloride is not as great when the oxygen concentration in the coolant is lowl thus, the higher limit 9n chlorides is permit ted during f ull power operation. During shutdown and refueling operations, the temperature necessary for, st ress corrosion to occer is not present. Conduct ivi ty measurement s ere required on a continuous basis since changes in this parameter are an !ndication of abnormal conditions. When the conductivity is within limit s, the pH, chlorides, and other impurities af fecting conductivity must also be within their a,ceptable limit s. With the conductivity outside the limits, additional samples must be examined to ensure
.that the chlorides are not exceeding the limits.
BRUNSWICK - UNIT 1 B 3/4 4-2 Ame nd me nt No. __ _ ~_ .__ _ _ ,_ ,. _ _ . . _ _ _ _ _ _
. .. --._.-- . . -.- - ._ =, - . - - - . ~ . . . . . . . . . . . - _ . - . . - . - - - _ . _ - -
l i J . ENCLOSURE 2 BRUNSWICK STEAM EL2CTRIC PIANT, UNITS 1 AND 2 NRC DOCKETS $0 325 6 50 324 OPERATING LICENSES DPR 71 & DPR 62 REQUEST FOR LICENSE AMENDMENT ICSCC REQUIREMENTS i TECHNICAL SPECIFICATIONS PAGES UNIT 2 i l 9
')
l l l
- . _ __. . _ _ _ . . _ . __ ____ _. - _ _m . . . _ _ _ _ . - _ . 1 APPLICABILITY SURVEILLANCE REQUIREMENTS 4.0.1 Surveillance Requirements shall be applicable during the OPERATIONAL CONDITIONS or other states specified f or individual Limiting Conditions for Operation unless otherwise stated in an individual Surveillance Requirement. 4.0.2 Each Surveillance Requirement shall be perf ormed within the specified time interval with a maximum allowable extension not to exceed 25% of the surveillance interval. 4.0.3 Performance of a Surveillance Requirement within the specified time interval shall constitute compliance with OPERABILITY requirements for a Limiting Condition for Operation and associated ACTION statements unless otherwise required by the specification. Surveillance requirements do not have to be performed on inoperable equipment. 4.0.4 Entry into an OPERATIONAL CONDITION or other specified applicable state shall not be made unless the Surveillance Requirement (s) associated with the Limiting Condition f or Operation have been performed within the applicable surveillance interval or as otherwise specified. 4.0.5 Surveillance Requirements for inservice inspection and testing of ASME Code Class 1, 2, and 3 com ,onents shall be applicable as follows: '
- a. Inservice inspection of ASME Code Class 1, 2, and 3 components and inservice testiag of ASME Code Class 1, 2, and 3 pumps and valves shall be perfermed in accordance with Section XI of the ASME Bolls r and Pressure Vessel Code and applicable Addenda as required by 10 CFR 50, Section 50.55a(g), except where specific written relief has bien granted by the Commission pursuant to 10 CFR 50, Section 50.55a(gi (6)
(1). BRUNSWICK - UNIT 2 3/4 0-2 Ame nd me n t No.
4 3/4.0 APPLICABILITY SURVEILLANCE REQUIREMENTS (Continued)
- b. Surveillance intervals specified in Section XI of the ASME Boiler and Pressure Vessel. Code and applicable Addenda for the inservice inspection and testing activities required by the ASME Boller and Pressure Vessel Code and applicable Addenda shall be applicable as follows in these Technical Specifications:
ASME Boiler and Pressure Vessel Required frequencies Code and applicable Addenda for performing inservice terminology for inservice inspection and testing ' inspection and testing activities activities Weekly At least once per 7 days Monthly At least once per 31 days Quarterly or every 3 months At least once per 92 days Semiannually or every 6 months At least once per 184 days Yearly or annually At least once per 366 days
- c. The provisions of Specification 4.0.2 are applicable to the above required frequencies for performing inservice inspection and testing activities.
- d. Performance of the above inservice' inspection and testing activities shall be in addition to other specified Surveillance Requirements.
- e. Nothing in.the ASME Boiler and Pressure Vessel Code shall be const rued to supersede the requirements of any Technical Specification.
- f. The Inservice Inspection Program for piping identified in NRC Ceneric Letter 88-01 shall be performed in accordance with the staff positions on schedule, methods & personnel 6 sample expansion inicuded in this letter.
BRUNSWICK - UNIT 2 3/4 0-3 Amendment No.
REACTOR COOLANT SYSTEM 4 OPERATIONAL LEAKACE l LIMITINC CONDITION FOR OPERATION 3.4.3.2 React or coolan't system leakage shall be limited tot
- a. No PRESSURE BOUNDARY LEAKAGE.
- b. 5 gpm UNIDENTIFIED LEAKACE averaged ovoc any 24-hour period.
- c. 25 gpm t ot al leakage averaged over any 24-hour period.
- d. 2 gpm increase in UNIDENTIFIED LEAKACE within any 24-hour period except f or the first 24 hours of reactor startup commencing with ent ry into OPERATIONAL CONDITION 2.
APPLICABILITY OPERATIONAL CONDITIONS 1, 2, and 3. ACTION
- a. With any PRESSURE BOUNDARY LEAKAGE. be in at least HOT SHUTDOWN within 12 hours and in COLD SHUTDOWN within the next 24 hours,
- b. With any reactor coolant system leakage greater than any one of the above limits, excluding PRESSURE BOUNDARY LEAKAGE, reduce the leakage rate to within the limits within 8 hours or be in at least HOT SHUTDOWN within the next 12 hours and in CouD SHUTDOWN within the following 24 hours.
SURVEILLANCE REQUIREMENTS 1 4.4.3.2 The reactor coolant system leakage shall be demonst rated to be within ! each of the above limits by!
- a. Monitoring the drywell and equipment drain sump flow rates.at least once per 8 hours, and
- b. Monitoring the primary containment atmosphere particulate and gaseous radioactivity at least once per 24 hours.
1 l l BRUNSWICK - UNIT 2 3/4 4-6 Amendment No. l l 1
APPLICABILITY BASES Under the terms of this specification, for example, during initial plant start-up or following extended plant outage, t he applicable surveillance activities must be performed within the st ated surveillance interval prior to placing or returning the system or equipment into OPERABLE status. Except ions to some surveillance activities have been provided for in individual specifications. 4.0.5 This specification ensures that inservice inspection et ASME Code Class 1, 2, and 3 components and inservice testing of ASME Code Class 1, 2 , and 3 pumps and valves will be perf ormed in accordante with a periodically updated version of Section XI of the ASME Boiler and Pressure Vessel Code and Addenda as required by 10 CFR 50. Section 50.55a. Relief from any ct the above requirements has been provided in writing by the Commission and is not a part of these technical specifications. This specification includei a clartlication of the frequencier for perf orming the inservice inspection and testing activities required by Section XI of the ASME Boiler and pressure Vessel Code and applicable Addenda. This claritication is provided to ensure consistency in surveillance intervals throughout these Technical Specifications and to remove any ambiguities relative to the f requencies f or perf orming the required inservice inspection and testing activities. Under the terms of this specification, the more restrictive requirements of the Technical Specifications take precedence over the ASME Botter and Pressure Vessel Code and applicable Addenda. For example, t he requi rement s of Specification 4.0.4 to perform surveillance activities prior to entry into an OPERATIONAL MODE or other specified applicabilit y condition takes precedence over the ASME Boiler and Pressure Vessel Code provision which allows pumps to be tested up to one week af ter return to normal operation. And, for example, the Technical Specification definition of OpCRABLE doe 6 not grant a grace period before a device that is not capable of perf orming its specified f unction is declared inoperable and takes precederce over the ASME Boiler and Pressure Vessel Code provision which allows a valve to be incapable of
- perf orming its speci fied f unction f or up to 24 hours bef ore being declared inoperable.
This specification includes a statement that the Inservice inspection Program for pipe overed by the scope of CL 88-01 will be in conformance with the staff positions on schedule, methods and personnel, and sampic expansion included in CL 88-01. This requirement may be removed form the technical specifications in the f uture in line with the Technical Specification Improvement programs. BRUNSWICK - UNIT 2 B 3/4 0-3 Amendment No. 1
REACT 0p. COOLANT SYSTEM BASES These specifications are based on the guidance of Cencral Elect ric 1 SIL #380, Rev. 1, 2-10-84. 3/4.4.2 SAFETY / RELIEF VALVES The reactor coolant system safety valve function of the safety-relief valves operate to prevent the system from being pressuriced above the Safety i Limit of 1325 psig. The system is designed to meet the requirements of the ASME Boiler and Pressure Vessel Code S'-*. ion !!! tor the pressure vessel and ANSI B31.1, 1967, Code for the reactos slant system piping. 3/4.4.3 REACTOR CCOLANT SYSTEM LEAKACE 3/4.4.3.1 LEAKAGE DETECTION SYSTEMS The RCS leakage detettion systems required by this specification are provided to monitor and detect leakage from the Reactor Coolant Pressure Boundary. These detection systems are consistent with the recommendations el Regulatory Guide 1.45, " Reactor Coolant Pressure Boundary Leakage Detection Systems." 3/4.4.3.2 OPERATIONAL LEAKACE P The allowable leakage rates of coolant f rom the reactor coolant system have been based on the predicted and experimentally observed behavior of cracks in pipes. The normally expected background leakage due to equipment design and the detection capability of the instrumentation for determining system' leakage was also considered. The evidence obtained f rom experiment s suggests that for leakage somewhat greater than. that specified for unidentified leakage, the probability is small that the imperfection or crack associated with such leakage would grow rapidly. However, in all cases, if the leakage rates exceed the values specified or the leakage is located and known to be PRESSURE BOUNDARY LEAKACE, the reactor will be shut down to allow turther investigation and corrective action. Monitoring leakage at eight hour intervals is in conformance with the 12/21/89 NRC SER for CL 88-01. 3/4.4.4 CHEMISTRY The reactor water chemistry limits are established to prevent damage to the reactor materials in contact with the coolant. Chloride limits are specified to prevent stress corrosion cracking of the stainless steel. The effect of chloride is not as great when the oxygen concentration in the coolant is lowl thus, the higher limit on chlorides is permitted during f ull power operation. During shutdown and refueling operations, the temperature necessary for st ress corrosion to occur is not present. Conductivity measurements are required on a continuous basis since changes in this parameter are an indication of abnormal conditions. When the conductivity is within limits, the pH, chlorides, and other impurities af fecting conductivity must also be within their acceptable limits. With the conductivity outside the limits. additional samples must be examined to ensure that the chlorides are not exceeding the limits. BRUNSWICK - UNIT 2 8 3/4 4-2 Amendment No.
4 I ENCI.h0URE 3 BRUNSk'ICK STEAM ELECTRIC PLANT, UNITS 1 AND 2 NRC DOCKETS 50 325 & $0 324 OPERATING LICENSES DPR 716 DPR 62 REQUEST FOR LICENSE AMENDMENT j IGSCC REQUIREMENTS l I INSTRUCTIONS FOR INCORPORATION 1hc proposed changes to the Technical Specifications (Appendix A to Operating Licenses DPR 71 and DPR 62) would be incorporated as follows: 1 UNIT 1-
' Remove Pa,gg insert Pace 3/4 02 3/4 02 3/4 03 3/4 03 3/4 46 3/4 46 B-3/4 03 B 3/4 03 B 3/4 42 B 3/4 42 ,
UNIT 2 , Remove Pa&R 1Daert Pare 3/4 02 3/4 02 3/4 03 3/4 03 3/4 46 + 3/4 46 B 3/4 03 B 3/4 03 B 3/4 42 B 3/4 42 i =. . . . . - _ - . - _ . . - - - - - . - . - - - - . - - - - . - - . - . . - . - . - - . . ..- . .-}}