ML20246K323
| ML20246K323 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 08/28/1989 |
| From: | Butler W Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20246K330 | List: |
| References | |
| NUDOCS 8909050435 | |
| Download: ML20246K323 (9) | |
Text
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION
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WASHINGTON, D. C. 20555
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PUBLICdERVICE ELECTRIC.&. GAS COMPANY ATLANTIC CLILELECTPlc. COMPANY DOCKEL NO..50.354 HOPE. CREEK. GENERATING. STATION AMENDMENL TQ.EACIllTLQPERAT.ING LICENSE l
Amendment No. 32 License No. NPF-57 1.
The Nuclear Regulatory Comission (the Comission or the NRC) has found that:
A.
The application for amendment filed by the Public Service Electric &
Gas Company (PSE&G) dated June 6,1989 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; 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 amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations set forth in 10 CFR Chapter I; D.
The issuance of this amendment will not be inimical to the comon 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 Specifica-tions as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-57 is hereby amended to read as follows:
(2) Techojcal. Specifications and_EnviroomentaLProtec14on Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 32, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license. PSE8G shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
8909050435 890828 PDR f-iDOCK 05000354 P
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- This license" amendment is effective.as of'its date of issuance and'shall
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be implemented within 60 days of the'dateof issuance.
FOR THE NUCLEAR'REGULATORYLCOMMISSION hl /
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L Walter.R. Butler,-Director.
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Project Directorate I-2
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Division of Reactor. Projects I/II-Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical-Specifications Da'te of. Issuance:. August 28, 1989 l
-. - - _. - -. - - - -. _ - -. _ ~ - -
45
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i ATTACHMENT TO l ' CENSE AMENDMENT NO.
32 FACILITY OPeaATING LICENSE NO. NPF-57 1
DOCKET N0. 50-354 1
1 Replace the following pages of the Appendix "A" Technical Specifications with the attached pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change. Overleaf pages provided to maintain document completeness.*
Remove Insert 3/4 6-1*
3/4 6-1*
3/4 6-2 3/4 6-2 3/4 6-3 3/4 6-3 3/4 6-4 3/4 6-4 3/4 6-41*
3/4 6-41*
3/4 6-42 3/4 6-42 i
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m 3/4.6 CONTAINMENT SYSTEMS' 3/4.6.1 PRIMARY CONTAINMENT PRIMARY CONTAINMENT INTEGRITY i
LIMITING CONDITION FOR OPERATION
- 3. 6.1.1 PRIMARY CONTAINMENT INTEGRITY shall be maintained.
l APPLICABILITY:
OPERATIONAL CONDITIONS 1, 2* and 3.
- ACTION:
Without PRIMARY CONTAINMENT INTEGRITY, restore PRINARY CONTAINMENT INTEGRITY within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTOOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
SURVEILLANCE REQUIREMENTS l
- 4. 6.1.1 PRIMARY CONTAINMENT INTEGRITY shall be demonstrated:
a.
'After each closing of each penetration subject to Type B testing, except the primary containment air locks, if. opened following Type A or 8 test, by leak rate testing the seals with gas at Pa, 48.1 psig, and verifying that when the measured leakage rate for these seals is d
added to the leakage rates determined pursuant to Surveillance Requirement 4.6.1.2.d for all other Type B and C penetrations, the combined leakage rate is less than or equal to 0.60 La.
l b.
At least once per 31 days by verifying that all primary containment penetrations ** not capable of being closed by OPERABLE containment automatic isolation valves and required to be closed during accident conditions are closed by valves, blind flanges, or deactivated automatic valves secured in position, except as provided in Table 1
3.6.3-1 of Specification 3.6.3.
c.
By verifying each primary containment air lock is in compliance with the requirements of Specification 3.6.1.3.
4 d.
By verifying the suppression chamber is in compliance with the requirements of Specification 3.6.2.1.
- See Special Test Exception 3.10.1 j
- Except valves, blind flanges, and deactivated automatic valves which are located i
l inside the primary containment, and are locked, sealed or otherwise secured in the closed position.
These penetrations shall be verified closed during each COLD SHUTDOWN except such verification need not be performed when the j
primary containment has not been de-inerted since the last verification or more often than once per 92 days.
HOPE CREEK 3/4 6-1 i
i
-., 7 3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT PRIMARY CONTAINMENT INTEGRITY LIMITING CONDITION FOR OPERATION 3.6.1.1 PRIMARY CONTAINMENT INTEGRITY shall be maintained.
APPLICABILITY: OPERATIONAL CONDTTIONS 1, 2* and 3.
1 ACTION:
Without PRIMARY CONTAINMENT INTEGRITY, restore PRIMARY CONTAINMENT INTEGRITY within I hour or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
SURVEILLANCE REQUIREMENTS 4.6.1.1 PRIMARY CONTAINMENT INTEGRITY shall be demonstrated:
a.
After each closing of each penetration subject to Type B testing, except the primary containment air locks, if opened following Type A or B test, by leak rate testing the seals with gas at Pa, 48.1 psig, and verifying that when the measured leakage rate for these seals is added to the leakage rates determined pursuant to Surveillance Requirement 4.6.1.2.d for all other Type B and C penetrations, the combined leakage rate is less than or equal to 0.60 La.
b.
At least once per 31 days by verifying that all primary containment penetrations ** not capable of being closed by OPERABLE containment automatic isolation valves and required to be closed during accident conditions are closed by valves, blind flanges, or deactivated automatic valves secured in position, except as provided in Table 3
3.6.3-1 of Specification 3.6.3.
c.
By verifying each primary containment air lock is in compliance with the requirements of Specification 3.6.1.3.
d.
By verifying the suppression chamber is in compliance with the requirements of Specification 3.6.2.1.
- See Special Test Exception 3.10.1 J
- Except valves, blind flanges, and deactivated automatic valves which are located
{
inside the primary containment, and are locked, sealed or otherwise secured in the closed position.
These penetrations shall be verified closed during each COLD SHUTDOWN except such verification need not be performed when the j
primary containment has not been de-inerted since the last verification or more often than once per 92 days.
j 1
HOPE CREEK 3/4 6-1 1
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CONTAINMENT SYSTEMS PRIMARY CONTAINMENT LEAKAGE LIMITING CONDITION FOR OPERATION 3.6.1.2 Primary containment leakage rates shall be limited to:
An overall integrated leakage rate of less than or equal to L, 0.5 per-a.
cent by weight of the containment air per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at P, 48 y a
3 p {g, b.
A combined leakage rate of less than or equal to 0.60 L for all penetrations and all valves listed in Table 3.6.3-1, exdept for main steam line isolation valves *, valves which form the boundary for the long-term seal of the feedwater lir.es, and other valves which are hydrostatically tested per Table 3.6.3-1, subject to Type B and C tests when pressurized to F ' 40'1 psi 9' a
- Less than or equal to 46.0 scfh combined through all four main steam c.
lines when tested at 5 psig (seal system AP).
d.
A combined leakage rate of less than or equal to 10 gpm for all con-tainment isolation valves which form the boundary for the long-term seal of the feedwater lines in Table 3.6.3-1, when tested at 1.10 Pa, 52.9 psig.
A coCined leakage rate of less than or equal to 10 gpm for all other e.
penetrations and containment isolation valves in hydrostatically l
tested lines in Table 3.6.3-1 which penetrate the primary contain-ment., when tested at 1.10 Pa, 52.9 psig Ap.
l APPLICABILITY: When PRIMARY CONTAINMENT INTEGRITY is required per Specification 3.6.1.1.
ACTION:
With:
The measured overall integrated primary containment leakage rate a.
exceeding 0.75 L or 3
b.
The measured combined leakage rate for all penetration ~s and all valves listed in Table 3.6.3-1, except for main steam line isolation valves *, valves which form the boundary for the long-term seal of the feedwater lines, and other valves which are hydrostatically tested per Table 3.6.3-1, suoject to Type B and C tests exceeding 0.60 L '
I a
c.
The measured leakage rate exceeding 46.0 scfh combined through all four main steam lines, or
'u d.
The measured combined leakage rate for all containment isolation valves which form the boundary for the long-term seal of the feedwater lines in Table 3.6.3-1 exceeding 10 gpm, or e.
The measured combined leakage rate for all other penetrations and l
containment isolation valves in hydrostatically tested lines in Table 3.6.3-1 which penetrate the primary containment exceeding 10 gpm, restore:
a.
The overall integrated leakage rate (s) to less than or equal to 0.75 L, and a
- Exemption to Appendix "J" of 10 CFR 50.
HOPE CREEK 3/4 6-2 Amendment No. 32
1 1.
CONTAINMENT SYSTEMS
{
LIMITING CONDITION FOR OPERATION (Continued)
ACTION (Continued) b.
The combined leakage rate for all penetrations and all valves listed in Table;3.6.3-1, except for main steam line isolation valves *, valves which form the boundary for the long-term seal of the feedwater lines, and other valves which are hydrostatically tested per Table 3.6.3-1, subject to Type 8 and C tests to less than or equal to 0.60 L,,
and The leakage rate to less than or equal to 46.0 scfh combined through ^
c.
L all four main. steam lines, and d.
The combined leakage rate for all containment isolation valves which form the boundary for the long-term seal of the feedwater lines in Table 3.6.3-1 to less than or equal to 10 gps, and The combined leakage rate for all other penetrations and codainment l
e.
isolation valves in hydrostatically tested lines in Table 3.6.3-1 which penetrate the primary containment to less than or equal to 10 gpm, prior to increasing reactor coolant system temperature above 200'F.
SURVEILLANCE REQUIREMENTS
- 4. 6.1. 2 The primary containment leakage rates shall be demonstrated at the following test schedule and shall be determined in conformance with the criteria specifled in Appendix J of 10 CFR 50 using the methods and provisions of ANSI N45.4 - 1972:
Three Type A Overall Integrated Containment Leakage Rate tests shall a.
be conducted at 40 + 10 month intervals during shutdown at P,,
48.1 psig, during each 10 year service period.
The third test of each set shall be conducted during the shutdown for the 10 year plant inservice inspection, b.
If any periodic Type A test fails to meet 0.75 L,, the test schedule for subsequent Typt' A tests shall be reviewed and approved by the Commission.
If two consecutive Type A tests fail to meet 0.75 L,, a Type A test shall be perforced at least every 18 months until two consecutive Type A tests meet 0.75 L, at which time the above test a
schedule may be resumed, The accuracy of each Type A test shall be verified by a supplemental c.
test which:
1.
Confirms the accuracy of the test by verifying that the difference between the supplemental data and the Type A test data is within 0.25 L,.
2.
Has duration sufficient to establish accurately the change in leakage rate between the Type A test and the supplemental test.
3.
Requires the quantity of gas injected into the containment or bled from the containment during the supplemental test to be between 0.75 L, and 1.25 L,.
- Exemption to Appendix "J" of 10 CFR 50.
HOPE CREEK 3/4 6-3 Amendment No. 32
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.1 CONTAINMENT SYSTEMS i
R SURVEILLANCE' REQUIREMENTS (Continued)
The formula to be used is: [L, + L,,- 0.25 L,] i Lcib*l o
am 0.25 L,] where L 5 supplement test _ result; L3 = superimposed leakage; c
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and'L, a measured Type A leakage.
Type B and C tests shall be conducted with gas at P,, 48.1 psig*,
d.
" a't intervals no greater than 24 months ** except for tests involving:
1.
Air locks, L,
2.
Main steam line isolation valves, 3.
Valves pressurized with~ fluid from a seal system, 4.
All containment isolation valves in hydrostatically tested lines in Table 3.6.3-1 which penetrate the primary containment, and l
5.
Purge supply and exhaust isolation valves with resilient material seals.
Air locks shall be tested and demonstrated OPERABLE per Surveillance e.
Requirement 4.6.1.3.
I f.
Main steam line isolation valves shall be leak tested at least once per 18 months.
g.
Containment isolation valves which fo'rm the boundary for the long-term seal of. the feedwater lines in Ta.ble 3.6.3-1 shall be hydrostati-cally tested at 1.10 P,, 52.9 psig, at least once per 18 months.
i h.
All containment isolatien valves in hydrostatically tested lines in Table 3.6.3-1 which penetrate the primary containment shall be leak tested at least once per 18 months.
j i.
Purge supply and exhaust isolation valves with resilient material seals shall be tested and demonstrated OPERABLE per Surveillance Requirements 4
4.6.1.8.2.
l 1
j.
The provisions of Specification 4.0.2 are not applicable to Specifications 4.6.1.2.a, 4.6.1.2.b, 4.6.1.2.c, 4.6.1.2.d, and 4.6.1.2.e.
- Unless a hydrostatic test is required per Table 3.6.3-1.
- A type C test interval extension to the first refueling outage is j
permissible for primary containment isolation valves listed in Table 3.6.3-1, which are identified in Public Service Electric & Gas Ccmpany's letter to the i
NRC (letter No. NLR-N87047), dated April 3, 1987, as needing a plant outage to test.
For this one time test interval, the requirements of Section 4.0.2 are not applicable.
HOPE CREEK 3/4 6-4 Amendment No. 32 1
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TABLE 3.6.3 PRIMARY CONTAINMENT ISOLATION VALVES NOTES NOTATION 1.,
Main Steam Isolation Valves are sealed with a seal system that maintains a positive pressure of 5 psig above reactor pressure.
Leaka0e..is in-leakage and is not added to 0.60 La allowable leakage.*
2.
Containment Isolation Valves are sealed with a water seal from the HPCI and/or RCIC system to form the long-term seal boundary of the feedwater lines.
The valves are tested with water'at 1.10 Pa, 52.9 psig, to ensure the seal "oundary will prevent by-pass leakage.- Seal boundary liquid leakage will be limited to 10 gpm.
3.
Containment Isolation Valve, Type C gas test at Pa, 48.1 psig.
Leakage added to 0.60La allowable leakage.
4.
ContainmentIsolationValve,TypeCwatertestat1.10Pa,52.9psigaP.l Leakage added to 10 gpm allowable leakage.
5.
Containment boundary is discharge nozzle of relief valve, leakage tested during Type A test.*
6.
Drywell and suppression chamber pressure and level instroment root valves and excess flow check valves, leakage tested during Type A.*
7.
Explosive shear valves (SE-V021 through SE-V025) not Type C tested.*
~
8.
Surveillance to be performed per Specification 3.6.1.8.
9.
All valve I.D. numbers are preceded by a numeral I which represents an Unit 1 valve.
- 10. The reactor vessel head seal leak detection line (penetration J5C) excess flow theck valve (BB-XV-3649) is not subject to OPERABILITY testing.
This valve will not be exposed to primary system pressure except under the unlikely conditions of a seal failure where it could be partially pressurized to reactor pressure.,
Any leakage path is restricted at the source; therefore, this valve need not be OPERABILITY tested.
- Exemption to Appendix J of 10 CFR Part 50.
HOPE CREEK 3/4 6-42 Amendment No. 32 l
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