ML18016A594

Proposed Tech Specs 3/4.6.3, Containment Air Locks for Consistency with NUREG-1431,Rev 1 & Clarifying Requirements for Locking Air Lock Door Shut

ML18016A594
Person / Time
Site:	Harris
Issue date:	09/23/1998
From:	CAROLINA POWER & LIGHT CO.
To:
Shared Package
ML18016A593	List: ML18016A592 ML18016A594
References
RTR-NUREG-1431 NUDOCS 9809280281
Download: ML18016A594 (18)

Text

ENCLOSURE 5 TO SERIAL: HNP-98-091 SHEARON HARRIS NUCLEAR POWER PLANT DOCKET NO. 50-400/LICENSE NO. NPF-63 REQUEST FOR LICENSE AMENDMENT TECHNICALSPECIFICATIONS 3/4.6.1.3 TECHNICALSPECIFICATION PAGES Page E5-1 eS09aS0aSZ 9S0923 PDR ADQCK 05000400 P PDR

CONTAINMENT SYSTEMS CONTAINMENT AIR LOCKS I

LIMITING CONDITION FOR OPERATION 3.6. 1.3 (IA0 Each containment air lock shall be OPERABLE ~

a IRCh-d N norm8-tmnsi4mnbvy-an~through-themonta Tnmen~he~t l a-A-4e-c lied ,and leakage-pale-ef ck less-Wan-er-equal-4e-0-.05-L, APPLICABILITY: MODES 1, 2. 3, and 4.

ACTION:

~er+ R

a. With one containment air lock door inoperable: g

l. intain a least th OPERABLE ir lock oor clos d* and dec. O" e her resto the ino erable ai lock do r to OP BLE c.o~W~~~~ ~ st us within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> r lock the OPERABL air loc door clos d; hockS

2. Operat'on may the continue until per rmance the n t require overall ai lock le age test ovided at th OPERABLE air lock do r is veri ied to be ocked c sed a least onc per 31 day;

+X Otherwise. be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hour~

aRcl

$ g. The provisions of Specification 3.0.4 are not applicable.

th the containmen air loc inoper le, ex pt as e res t of an 'noper le air loc door. intain t leas one ai lock d r I clos d; res re the ino rable 'r lock o OPE LE st us wit 'n C 24 ho s or be 'n at leas HOT S NDBY wi hin th ext 6 ours a d in COLD UTDOWN ithin th followi g 30 h rs.

SHEARON HARRIS - UNIT 1 3/4 6-4

CONTAINMEHT SYSTEMS CONTAINHEHT AIR LOCKS SURVEILlANCE RE UIRENEHTS by 4.6.1.3 Each containment air lock shall be demonstrated OPERABLE:

'a ~ Within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> fol o~ing each losing, except when the air lock is bei g used for mu iple entri , then at 1 1st once per 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />, by v ifying seal akage is 1 s than 0.01 as deter@in by pre-a ision flow asurements en measure for at least seconds w h the volume etween the als at a c stant pressur of 41 psig; By cond ting overa air lock akage tests at ot less tha P, 1

and v ifying the overall air ock leakage r e is within ts limit:

l. At least nce per 6 m ths," and Prior to establis 'ng CONTAIHMEHT" HTEGRITY whey maintenance hW een perform d on the air 1 ck that could dffect the air lo k sealing ca ability.""

At least once per 6 months by verifying tha only one door in each air lock can be opened at a time~+<

"Thy provi ons oP Spec'catji in 4.0. re neo applicable.

his preseng an emptidn to A endixg para'(aph IIIA.2 of'104R Pa/SO.

SHEARON HARRIS " UNIT 1 3/4 6"5

Insert, "A" Notes

l. Entry and exit is permissible to perform repairs on the affected air lock components.

2. A separate ACTION is allowed for each air lock.

3. Enter 3.6.1.1 LCO for "Containment Integrity" when the air lock leakage results in exceeding the overall containment leakage rate, Specification 3.6.1.2.a.

Locking a Personnel Air Lock door shut consists of locking the associated manual pumping stations and deactivating the electronic mechanisms used to open a Personnel Air lock door once the associated air lock door is shut. Locking an Emergency Air Lock doors shut consists of locking the mechanical operator.

Insert "B"

1. Within one hour, verify the OPERABLE door is closed in the affected air lock, and

2. Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, lock the OPERABLE door closed in the affected air lock, and

3. Once per 31 days, verify the OPERABLE door is locked closed in the affected air lock*, or

Insert "C" I

¹ 1 - ACTIONS 3.6.1.3.a. 1, 3.6.1.3.a.2, 3.6.1.3.a.3, and 3.6.1.3.a.4 are not applicable if both doors in the same air lock are inoperable and ACTION 3.6.1.3.c is entered.

2.- Entry and exit is permissible for 7 days under administrative controls ifboth air locks are inoperable.

Air lock doors in high radiation areas may be verified closed by administrative means.

Insert "D"

b. One or more containment air locks with containment air lock interlock mechanism inoperable.¹¹

1. Within one hour, verify an OPERABLE door is closed in the affected air lock, and

2. Within 24 hous, lock an OPERABLE door closed in the affected air lock, and

3. Once per 31 days, verify the OPERABLE door is locked closed in the affected air lock~, or

4. Otherwise, be in HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

Provisions of Specification 3.0.4 are not applicable.

c. One or more containment air locks inoperable for reasons other than 3.6.1.3.a or 3.6.1.3.b.

1. Immediately initiate action to evaluate overall containment leakage rate per LCO 3.6.1.2, and

2. Within one hour, verify a door is closed in the affected air lock, and

3. Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, restore air lock to OPERABLE status, or

4. Otherwise be in HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

¹¹ l. - ACTIONS 3.6.1.3.b. 1, 3.6.1.3.b.2, 3.6.1.b.3, and 3.6.1.3.b.4 are not applicable ifboth doors in the same air lock are inoperable and ACTION 3.6.1.3.c is entered.

2.- Entry and exit of containment is permissible under the control of a dedicated individual.

Air lock doors in high radiation areas may be verified closed by administrative means.

Insert "E"

a. Performing required air lock leakage rate testing in accordance with 10 CFR 50, Appendix J, as modified by approved exemptions ¹¹¹. The acceptance criteria for air lock testing are:

1. Overall air lock leakage rate is (.05 La when tested at > Pa.

2. For each door, leakage rate is (.01 La when tested at > 41 psig.

Insert "F"

¹¹¹ 1. An inoperable air lock door does not invalidate the previous successful performance of the overall airlock leakage test.

2. Results shall be evaluated against Specification 3.6.1.2.a in accordance with 10 CFR 50, Appendix J, as modified by approved exemptions.

Only required to be performed upon entry or exit through the containment air lock. (IfSurveillance Requirement 4.6.1.3.b has not been perfomed in the last 6 months, then perform Surveillance Requirement 4.6.1.3.b during the next containment entry through the associated air lock.)

3/4.6 CONTAINM SYSTEMS BASES 3/4.6. 1 PR IHARY CONTAINMENT 3/4.6. 1. 1 CONTAINMENT INTEGRITY Primary CONTAINMENT INTEGRITY ensures that the release of radioactive materials from the containment atmosphere will be restricted to those leakage paths and associated leak rates assumed in the safety analyses. This restriction. in conjunction with the leakage rate limitation. will limit the SITE BOUNDARY radiation doses to within the dose guideline values of 10 CFR Part 100 during accident conditions.

3/4.6. 1. 2 CONTAINMENT LEAKAGE The limitations on containment leakage rates ensure that the total containment leakage volume will not exceed the value assumed in the safety analyses at the peak accident pressure. P,. As an added conservatism, the measured overall integrated leakage rate is further limited to less than or equal to 0.75 L,,

during performance of the periodic test. to account for possible degradation of the containment leakage barriers between leakage tests.

The surveillance testing for measuring leakage rates is consistent with the requirements of Appendix J of 10 CFR Part 50.

A one time extension of the test interval specified in Surveillance Requirement 4.6. 1.2.a is allowed for performance of the third Type A test of the first 10-year service period during Refueling Outage No. 7.

'3/4.6.1. 3 CONTAINMENT AIR LOCKS The limitations on closure and leak rate for the containment air locks are required to meet the restrictions on CONTAINMENT INTEGRITY and containment leak rate. Surveillance testing of the air lock seals provides assurance that the overall air lock leakage will not become excessive due to seal damage during the intervals between air lock leakage tests.

maeve >

3/4.6. 1.4 INTERNAL PRESSURE The limitations on containment internal pressure ensure that: (1) the containment structure is prevented from exceeding its design negative pressure differential with respect to the outside atmosphere of -2 psig, and (2) the containment peak pressure does not exceed the design pressure of 45 psig.

The maximum peak pressure expected to be obtained from a postulated main steam line break event is 41.2 psig using a value of 1.9 psig for initial positive containment pressure. However. since the instrument tolerance for containment ressure is 1.32 psig and the high-one setpoint is 3.0 psig. the pressure imit was reduced from the high-one setpoint by slightly more than the tolerance and was set at 1.6 psig. This value will prevent spurious safety injection signals caused by instrument drift during normal operation. The

-1" wg was chosen to be consistent with the initial assumptions of the accident analyses.

HNP-96-064 SHEARON HARRIS - UNIT 1 B 3/4 6-1

Insert "G" in Bases Action statement "a" has been modified by a note. The note allows use of the air lock for entry and exit for seven days under administrative controls ifboth air locks have an inoperable door.

This seven day restriction begins when a door in the second air lock is discovered to be inoperable. Containment entry may be required to perform Technical Specification surveillances and actions, as well as other activities on equipment inside containment that are required by Technical Specifications (TS) or other activities that support TS required equipment. In addition, containment entry may be required to perform repairs on vital plant equipment, which ifnot repaired, could lead to a plant transient or a reactor trip. This note is not intended to preclude performing other activities (i.e., non-TS required activities or repairs on non-vital plant equipment) if the containment is entered, using the inoperable air lock, to perform an allowed activity listed above. This allowance is acceptable due to the low probability of an event that could pressurize containment during the short time that an OPERABLE door is expected to be open.

Maintaining containment air locks OPERABLE requires compliance with the leakage rate test requirements of 10 CFR 50, Appendix J, as modified by approved exemptions. HNP has an approved exemption to Appendix J Option A, paragragh III.D.2 of 10 CFR 50 in that the Overall air lock leakage test is required to be performed ifmaintenance has been performed that could affect the air lock sealing capability prior to establishing CONTAINMENTINTEGRITY. This is in contrast to the Appendix J requirement ifair locks are opened during periods when containment integrity is not required by the plant's Technical Specifications shall be tested at the end of such periods.

CONTAINMENT SYSTEMS CONTAINMENT AIR LOCKS LIMITING CONDITION FOR OPERATION 3.6.1.3 Two containment air locks shall be OPERABLE:

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTION:

~ 0 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ Notes

1. Entry and exit is permissible to perform repairs on the affected air lock components.

2. A separate ACTION is allowed for each air lock.

3. Enter 3.6, 1. 1 LCO for "Containment Integrity" when the air lock leakage results in exceeding the overall containment leakage rate, Specification 3.6.1.2.a.

Locking a Personnel Air Lock door shut consists of locking the associated manual pumping stations and deactivating the electronic mechanisms used to open a Personnel Air Lock door once the associated air lock door is shut. Locking an Emergency Air Lock door shut consists of locking the mechanical operator.

a. One or more containment air locks with one containment air lock door inoperable:8

1. Within one hour, verify the OPERABLE door is closed in the affected air lock, and

2. Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, lock the OPERABLE door closed in the affected air lock, and

3. Once per 31 days, verify the OPERABLE door is locked closed in the affected air lock*, or

4. Otherwise, be in HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

5. Provisions of Specification 3.0.4 are not applicable.

1. ACTIONS 3.6.1.3.a.l, 3.6.1.3.a.2, 3.6.1.3.a.3, and 3.6.1.3.a.4 are not applicable if both doors in the same air lock are inoperable and ACTION 3.6. 1.3.c is entered.

2. Entry and exit is permissible for 7 days under administrative controls if both air locks are inoperable.

Air lock doors in high radiation areas may be verified closed by administrative means.

SHEARON HARRIS - UNIT 1 3/4 6-4 Amendment No.

CONTAINMENT SYSTEMS CONTAINMENT AIR LOCKS LIMITING CONDITION FOR OPERATION

b. One or more containment air locks with containment air lock interlock mechanism inoperable.88

1. Within one hour, verify an OPERABLE door is closed in the affected air lock, and

2. Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, lock an OPERABLE door closed in the affected air lock, and Once per 31 days, verify the OPERABLE door is locked closed in the affected air lock*, or

4. Otherwise, be in HOT STANDBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

5. Provisions of Specification 3.0.4 are not applicable.

C. One or more containment air locks inoperable for reasons other than 3.6. 1.3.a or 3.6. 1.3.b.

Immediately initiate action to evaluate overall containment leakage rate per LCO 3.6. 1.2, and

2. Within one hour, verify a door is closed in the affected air lock, and

3. Within 24 hours, restore air lock to OPERABLE status, or 4, Otherwise be in HOT STANDBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

8P 1. ACTIONS 3.6.1.3.b.l, 3.6.1.3.b.2, 3.6.1.3.b.3, and 3.6.1.3.b.4 are not applicable if both doors in the same air lock are inoperable and ACTION 3.6. 1.3.c is entered.

2, Entry and exit of containment is permissible under the control of a dedicated individual.

• Air lock doors in high radiation areas may be verified closed by administrative means.

SHEARON HARRIS - UNIT 1 3/4 6-4a Amendment No.

CONTAINMENT SYSTEMS CONTAINMENT AIR LOCKS SURVEILLANCE REQUIREMENTS 4.6. 1.3 Each containment air lock shall be demonstrated OPERABLE by:

a ~ Performing required air lock leakage rate testing in accordance with 10 CFR 50, Appendix J, as modified by approved exemptions8PP.

The acceptance criteria for air lock testing are:

1. Overall air lock leakage rate is < .05 La when tested at > Pa.

2. For each door, leakage rate is < .01 La when tested at > 41 pslg.

At least once per 6 months by verifying that only one door in the air lock can be opened at a time**.

PIP 1. An inoperable air lock door does not invalidate the previous successful performance of the overall airlock leakage test.

2. Results shall be evaluated against Specification 3.6. 1.2.a in accordance with 10 CFR 50, Appendix J, as modified by approved exemptions.

• • Only required to be performed upon entry or exit through the containment air lock. ( If Surveillance Requirement 4.6. 1.3.b has not been performed in the last 6 months, then perform Surveillance Requirement 4.6. 1.3.b during the next containment entry through the associated air lock.)

SHEARON HARRIS - UNIT 1 3/4 6-5 Amendment No.

3 4.6 CONTAINMENT SY MS BASES 3 4.6'.1 PRIMARY CONTAINMENT 3 4.6.1.1 CONTAINMENT INTEGRITY Primary CONTAINMENT INTEGRITY ensures that the release of radioactive materials from the containment atmosphere will be restricted to those leakage paths and associated leak rates assumed in the safety analyses. This restriction, in conjunction with the leakage rate limitation, will limit the SITE BOUNDARY radiation doses to within the dose guideline values of 10 CFR Part 100 during accident conditions' 4.6. 1.2 CONTAINMENT LEAKAGE The limitations on containment leakage rates ensure that the total containment leakage volume will not exceed the value assumed in the safety analyses at the peak accident pressure, P,. As an added conservatism, the measured overall integrated leakage rate is further limited to less than or equal to 0.75 L.,

during performance of the periodic test, to account for possible degradation of the containment leakage barriers between leakage tests.

The surveillance testing for measuring leakage rates is consistent with the requirements of Appendix J of 10 CFR Part 50.

A one time extension of the test interval specified in Surveillance Requirement 4.6. 1.2.a is allowed for performance of the third Type A test of the first 10-year service period during Refueling Outage No. 7.

3 4.6.1.3 CONTAINMENT AIR LOCKS The limitations on closure and leak rate for the containment air locks are required to meet the restrictions on CONTAINMENT INTEGRITY and containment leak rate. Surveillance testing of the air lock seals provides assurance that the overall air lock leakage will not become excessive due to seal damage during the intervals between air lock leakage tests.

Action statement "a" has been modified by a note. The note allows use of the air lock for entry and exit for seven days under administrative controls if both air locks have an inoperable door. This seven day restriction begins when a door in the second air lock is discovered to be inoperable.

Containment entry may be required to perform Technical Specification surveillances and actions, as well as other activities on equipment inside containment that are required by Technical Specifications (TS) or other activities that support TS, required equipment. In addition, containment entry may be required to perform repairs on vital plant equipment, which if not repaired, could lead to a plant transient or a reactor trip. This note is not intended to preclude performing other activities (i.e., non-TS required activities or repairs on non-vital plant equipment) if the containment is entered, using the inoperable air lock, to perform an allowed activity listed above. This allowance is acceptable due to the low probability of an event that could pressurize containment during the short time that an OPERABLE door is expected to be open.

SHEARON HARRIS - UNIT 1 8 3/4 6-1 Amendment No.

3 4.6 CONTAINMENT SY MS BASES CONTAINMENT AIR LOCKS Continued Maintaining containment air locks OPERABLE requires compliance with the leakage rate test requirements of 10 CFR 50, Appendix J, as modified by approved exemptions. HNP has an approved exemption to Appendix J Option A, paragraph III.D.2 of 10 CFR 50 in that the Overall air lock leakage test is required to be performed if maintenance has been performed that could affect the air lock sealing capability prior to establishing CONTAINMENT INTEGRITY.

This is in contrast to the Appendix J requirement if air locks are opened during periods when containment integrity is not required by the plant's Technical Specifications shall be tested at the end of such periods.

3 4.6.1.4 INTERNAL PRESSURE The limitations on containment internal pressure ensure that: (1) the containment structure is prevented from exceeding its design negative pressure differential with respect to the outside atmosphere of -2 psig, and (2) the containment peak pressure does not exceed the design pressure of 45 psig.

The maximum peak pressure expected to be obtained from a postulated main steam line break event is 41.2 psig using a value of 1.9 psig for initial positive containment pressure. However, since the instrument tolerance for containment pressure is 1.32 psig and the high-one setpoint is 3.0 psig, the pressure limit was reduced from the high-one setpoint by slightly more than the tolerance and was set at 1.6 psig. This value will prevent spurious safety injection signals caused by instrument drift during normal operation. The

-1" wg was chosen to be consistent with the initial assumptions of the accident analyses.

SHEARON HARRIS - UNIT 1 8 3/4 6-la Amendment No.

t I*

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