ML20248D939
| ML20248D939 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 08/01/1989 |
| From: | NORTHEAST NUCLEAR ENERGY CO. |
| To: | |
| Shared Package | |
| ML20248D936 | List: |
| References | |
| GL-83-36, NUDOCS 8908110173 | |
| Download: ML20248D939 (7) | |
Text
_,
Docket No. 50-245 B13297 l,
I Atta:hment 1 Millstone Unit No. 1 Proposed License Amendment Generic Letter 83-36 Technical Specifications August 1989 8908110173 890801 PDR ADOCK 05000245 P
+
i LIflITING CONDITION FOR OPERATION 3.7 CONTAINMENT SYSTEMS 3.7. A.3.a Primary containment integrity, as defined in Section 1.0, shall be l
maintained at all times when the reactor is critical or when the.
reactor water temperature is above 212*F and fuel is in the reactor vessel.
- b. If Specification 3.7. A.3.a cannot be met, initiate an orderly shutdown and have the reactor in the COLD SHUTDOWN or REFUEL CONDITION within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
SURVEILLANCE REQUIREMENT 4.7.A.3.
The primary containment integrity shall be demonstrated as follows:
a.
Integrated Primary Containment Leak Test (IPCLT)
The containment leakage rates shall be demonstrated at the follow-ing test schedule and shall be determined in conformance with the criteria specified in Appendix J of 10 CFR 50 using the methods and provisions of ANSI N45.4-1972 and BN-TOP-1 1.
Three Type A Overall Integrated Containment Leakage Rate tests shall be conducted at 40110 month intervals during shutdown at P (43 psig) during each ten-year service period. The third test of each set shall be conducted during the shutdown for the ten-year plant inservice inspection.
2.
If any periodic Type A test fails to meet 0.75 L the test schedule for subsequent Type A tests shall be re$,ewed and i
approved by the Commission.
If two consecutive Type A tests fail to meet 0.75 L, a Type A test shall be performed at least every18monthsuntiltwoconsecutiveTypeAtestsmeet0.75 L,, at which time the above schedule may be resumed.
3.
The accuracy of each Type A test shall be verified by a supplemental test which:
a.
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
- a b.
Has duration sufficient to establish accurately the change in leakage rate between the Type A test and the supplemen-tal test.
c.
Requires the quantity of gas injected into containment or bled from containment during the supplemental test to be equivalent to at least 25 percent of the total measured leakage at P
- a Millstone Unit 1 3/4 7-4 Amendment No. JJ
LIMITING CONDITION FOR OPERATION
'3. 7 CONTAINMENT SYSTEMS
~
3.7.A.5.
Pressure suppression chamber - drywell vacuum breakers ~:
a.
When primary containment is required, all suppression chamber-drywell vacuum breakers shall be operable except during testing and as stated in Specification 3.7.A.S.b and c below.
Suppression chamber-drywell vacuum breakers shall be operable if:
(1) The valve is demonstrated to open fully with the applied force at all valve positions not exceeding that equivalent to 0.5 psi acting on the face of the valve disc.
(2) The valve can be closed by gravity, when released after being manually opened, to within not greater than 0.075 inch or less, as measured at the bottom of the valve disc.
(3) The position alarm system will annunciate in the control room if any valve opening exceeds the equivalent of 0.075 inch as measured at the bottom of the disc.
b.
Up to two (2) of the ten (10) suppression chamber-drywell vacuum breakers may be determined to be inoperable provided that they are secured, or known to be in the closed position.
c.
If Specification 3.7.A.5.a or b cannot be met, the situation shall be corrected within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, or the reactor shall be placed in the COLD SHUTDOWN or REFUEL CONDITION within the subsequent 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
6.
Oxygen concentration:
a.
After completion of the startup test program and demonstration of plant electrical output, the primary containment atmosphere shall be reduced to less than 4% oxygen with nitrogen gas whenever the reactor coolant pressure is greater than 90 psig and during reactor power operation except as specified in 3.7.A.6.b or 3.7.A.6.c.
b.
Within the 24-hour period subsequent to placing the reactor in the RUN mode following a shutdown, the containment atmosphere oxygen concentration shall be reduced to less than 4% by volume and maintained in this condition. Deinerting may commence 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to a shutdown.
c.
Oxygen concentration may be greater than 4% by volume for a period not to exceed 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> for purposes of conducting drywell entries relating to testing, surveillance, or maintenance on equipment important to safety.
d.
If Specification 3.7. A.6 cannot be met, initiate an orderly l
shutdown and have the reactor in the COLD SHUTDOWN or REFUEL CONDITION within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Millstone Unit I 3/4 7-8 AmendmentNo./
. ; LIMITING CONDITION FOR OPERATION (Continued)
^
^3.7 CONTAINMENT SYSTEMS 3.7.A.7.
Containment High Range Radiation Monitors:
a.
Two containment high range radiation monitors shall be OPERABLE whenever primary containment is required, except as specified in 3.7.A.7.b.
b.
With one or more of the. containment high range radiation monitors inoperable, initiate the preplanned alternate method of monitoring the appropriate parameter (s) within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, and i
either restore the inoperable channel (s) to OPERABLE status within 7 days, or prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next-14 days following the event outlining the action taken, the cause of the inoperability, and the. plans and schedule for restoring the system to OPERABLE status.
8.
Containment Pressure a.
At least one of the two wide range drywell pressure monitors shall be OPERABLE whenever primary. containment is required, l
except as specified in 3.7.A.8.b.
L b.
With the drywell pressure monitoring system inoperable, either restore at least one of the channels to OPERABLE status within 7 days, or prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 14 days following the event outlining the action taken, the cause of the inoperability, and the plans and schedule for restoring the system to OPERABLE status.
Millstone Unit 1 3/4 7-8a L
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-SURVEILLANCE REQUIREMENT 4.7 -CONTAINMENT SYSTEMS
- 4. 7.. A. 5.
Pressure suppresion chamber -'drywell vacuum breakers:
l a.
Periodic operability tests:
Once each month and following any release of energy to the l
suppression chamber, each suppression chamber-drywell vacuum breaker shall be exercised through one open and close cycle and visually inspected. Operability of valves, position switches and position indicators'and alarms shall be verified.
b.
Refueling outage tests:
(1) All suppression chamber-drywell vacuum breakers shall be tested to determine the force required to open each valve from fully closed to fully open.
(2) All suppression chamber-drywell vacuum breaker position indication and alarm systems shall be calibrated.
(3) At least two (2) of the suppression chamber-drywell vacuum breakers shall be inspected including internal components.
If seating or friction deficiencies are noted such that Specification 3.7.A.5 could not be met, all vacuum breakers shall be inspected, including internal components, and deficiencies corrected.
6.
Oxygen concentration:
Whenever.inerting is required, the primary containment oxygen concentration shall be measured and recorded on a weekly basis.
7.
Containment High Range Radiation Monitors:
Each containment high range radiation monitor shall be demonstrated OPERABLE by performance of a quarterly functional test and a channel calibration once per operating cycle.
8.
Containment Pressure:
Each containment pressure monitor shall be calibrated once per operating cycle.
1 i
. Millstone Unit 1 3/4 7-9
3.7 CONTAINMENT SYSTEMS J
JBASES containment is normally slightly pressurized during periods of reactor operation assuring no air in-leakage through the primary containment. However, at least once a week, the oxygen concentra-
)
tion will be determined as added assurance.
i 7.
Post-Accident Monitorino Instrumentation The containment pressure and high range radiation monitors ensure that additional information fs available to monitor and assess these varialles during and following an accident. This capability is consistent with the recommendations of NUREG-0737, " Clarification of TMI Action Plan Requirements," dated November,1980.
B.
Standby Gas Treatment Systems The standby-gas treatment system is designed to filter and exhaust the.
reactor building atmosphere to the stack during secondary containment-
' isolation conditions.
Both standby gas treatment system fans are p-designed to automatically start upon containment isolation and to main-tain the reactor building pressure to the design negative pressure so that all leakage should be in-leakage.
Each of the two fans has 100 percent capacity.
High efficiency particulate absolute (HEPA) filters are installed before and after the charcoal adsorbers to minimize potentiu release of partic-ulates to the environ 2cnt and to prevent clogging of the iodine adsorbers.
The charcoal should indicate a system leak tightness of less than 1 percent bypa s leakage for the charcoal adsorbers and a HEPA l
efficiency of at least 99 percent removal of D0P particulate. The l
laboratory carbon sample test results should indicate a radioactive I
methyl iodide removal efficiency of at least 95 percent for expected accident conditions.
If the efficiencies of the HEPA filters and char-coal adsorbers are as specified, the resulting do:es wil'. be less than the 10 CFR 100 guidelines fe the accidents analyzed. Operation of the fans' signify different from the design flow will change the removal efficiency of the HEPA filters and charcoal adsorbers.
Only one e < the two standby gas treatment systems is needed to clean up the reactor building atmosphere upon containment isolation.
If one system is found to be inoperable, there is no immediate threat to the containment system performance, and reactor Oper ation or refueling operation may continue while repairs are LW ng made. During refueling, two off-site power sources (345 KV or 273 AV) and ona emergency power source would provide an adequate and reliable source of power and allow complet'9n of annual diesel or gas turbine preventative maintenance.
Millstone Unit 1 B 3/4 7-5 AmendmentNo.[
ADMINISTRATIVE CONTROLS The report sh.11 include that information delineated in the REM 0DCM.
Any. changes to. the REM 0DCM 'shall be submitted in the Semiannual Radioactive Effluent Release Report.
Supplemental Reload Licensino Submittal 6.9.1.9 f ee power distribution limits (MCPA, LHGR, and APulGR) shall be established and documented in the Supplement Reload Licensing Submittal before each reload cycle or any remaining pset of a reload cycle.
The analytical methode used to determine these limits shall be those previously reviewe. and approW by the NRC in NEDE-24011, General Electric Standard Application for Reactor Fuel, latest approved revision.
.The core power distribution limits shall be determined so that all applicable limits (n.g.,
fuel thermal-mechanical. limits, ECCS limits, nuclear limits-such as shutdown margin, and transient and accident analyses limits) of the safety analysis are met.
The Supplemental Reload Licensing Submittal, including any mid-cycle revisions or supplements thereto, shall be submitted upon issuance.
~Special Reports 6.9.2 Special reports shall be sub.mitted to the U.S. Nuclear Regulatory Commission Document Control Desk, Washington, D.C.
20555, one copy l
to the Regional Administrator, Region I, and one copy to the NRC Resident Inspector, within the time period ;pecified for each report.. These reports shall be submitted covering the activities identified below pursuant to the requirement of the applicable reference specification:
a.
In-service Inspection Results, Specification 4.6.F.
b.
Primary Containment Leak Rate Test
- Results, Specifica-tion 4.7.A.3.
1 c.
Materials Radiation Surveillance Specimen Examination and Results, Specification 4.6.B.3.
d.
Fire detection instrumentation, Specification (3.12.E.2) e.
Fire suppression systems, Specifications (3.12. A.2, 3.12.B.2, and 3.12.C.2).
f.
Radiological Effluent Reports required by Specifications in 3.8.C.2, 3.8.D.2, 3.8.D.3, and 3.8.D.4.
g.
Containment High Range Radiation
- Monitors, Specification 3.7.A.~7.
h.
Containment Pressure, Specification 3.7.A.B.
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j' Millstone Unit 1 6-19 Amendment No. J, JJ
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