ML18012A562
| ML18012A562 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 03/17/1997 |
| From: | NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML18012A561 | List: |
| References | |
| NUDOCS 9703200196 | |
| Download: ML18012A562 (5) | |
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UNITED STATES NUCLEAR REGULATORYCOMMISSION WASHIN('TON, D.C. 205554001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION I
RELATED 0
ENDM N NO.
69 0
ACILITY OPERATING ICENSE NO. NPF-63 CAROLINA POWER
& LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 DOCKET NO. 50-400 1.0 NTRODUC ION By letter dated January 29,
- 1997, as supplemented February 6,
and February 21, 1997, the Carolina Power 8 Light Company (CP&L or the licensee) submitted a
request for changes to the Shearon Harris Nuclear Power Plant, Unit 1
(SHNPP),
Technical Specifications (TSs).
The February 6, and 21, 1997, letters provided clarifying information that did not change the initial proposed no significant hazards consideration determination.
The requested changes would add TS 3.0.5 and its associated Bases.
This new specification will revise the plant TS to provide specific guidance allowing equipment removed from service or declared inoperable to comply with ACTIONS to be returned to service under plant administrative control in order to perform the required testing to demonstrate its OPERABILITY or the OPERABILITY of other equipment.
This proposed change is functionally identical to the guidance provided in the current Standard Technical Specifications for Westinghouse
- Plants, NUREG-1431, Rev.
1.
- 2. 0 VALUATION The present TSs for SHNPP neither specifically allow nor prohibit re-entry into ACTION statements.
In the Standard Technical Specifications for Westinghouse
- Plants, NUREG-1431, Vol. 1, Rev.
1, the NRC staff approved a
provision, via TS 3.0.5 section, that establ,ishes the allowance for restoring equipment to service under plant administrative control when it has been removed from service or declared inoperable to comply with ACTIONS statement.
The sole purpose of this specification is to provide an exception to the limiting conditions for operation (LCO) 3.0. 1 (e.g., to not comply with the applicable Required Action(s) to allow the performance of surveillance requirements (SRs) to demonstrate:
a.
The OPERABILITY of the equipment being returned to service;.or b.
The OPERABILITY of other equipment.
9703200l96 9703i7 PDR ADQCK 05000400 P
Currently, the SHNPP TSs require that whee equipment has been out of service it is necessary to demonstrate that it can perform its required function, before it can be returned to service in an OPERABLE condition.
In its submittal, the licensee stated that most testing can be done prior to returning equipment to service, but in some cases it is necessary to return to a functional status in order to demonstrate an activity required for OPERABILITY.
A particular example for SHNPP is Specification 3.3.3.1, RADIATION MONITORING FOR PLANT OPERATIONS, items 1.b and 1.c of TS Table 3.3-6 that deal with containment airborne radioactivity monitors during normal and pre-, entry purge operation.
Each of these items has an ACTION statement which requires the associated purge valves to be maintained closed in the event the radiation monitor is inoperable, and in order to demonstrate the OPERABILITY of the radiation monitor prior to its return to service,'it is necessary to demonstrate that the associated purge valves will be automatically closed if a trip set point. is reached on the monitor.
However, the only way this test'an be performed is by opening the associated valves to observe their closing as a
result of the radiation monitor signal; and on the other hand, the valve cannot be opened because of the ACTION statement in force due to the INOPERABLE radiation monitor.
This creates a situation in which it can become logically impossible to demonstrate the operability of the radiation monitor; and thus, the requested
.change would resolve this situation by adding new TS 3.0.5 to provide an exception for the required compliance with ACTION statements of existing TS 3.0. 1.
For the above
- example, the new TS clarifies that it is permissible to open a purge valve in order to observe its closure by the functional radiation monitor signal.
The staff has reviewed the licensee's proposed change and concludes that the addition of TS 3.0.5 and its associated Bases is functionally consistent with NUREG-1431, provides clarification of the existing SHNPP's LCOs 3.0. 1 and 3.0.2, and maintains compliance with the intent of both LCO 3.0. 1 and 3.0.2.
The staff notes that in NUREG-1431, LCO 3.0.1 simply references LCO 3.0.2 for instances of noncompliance and does not mention ACTION statements.
The staff reviews the current SHNPP TS 3.0. 1 and finds it contains the phrase
"...upon failure to meet the Limiting Condition for Operation, the associated ACTION requirements shall be met."
Furthermore, the current SHNPP TS 3.0.2 states:
"Noncompliance wi.th a specification shall exist when the requirements of the Limiting Condition for Operation and the associated ACTION requirements are not met within the specified time intervals."
The staff finds the licensee's proposed new TS 3.0.5 is functionally similar to that of TS 3.0.5 in the staff-approved NUREG-1431, Rev.l, "Standard Technical Specifications for Westinghouse Plants,"
and concurs with the need for the licensee to have an exception to their current SHNPP TS 3.0. 1.
As stated in TS 3.0.5, this exception is solely intended to allow the performance of surveillance testing to demonstrate the operability of the equipment being returned to service; oi'he operability of other equipment.
Based on the above review, the staff finds that the licensee's proposed change to add TS 3.0.5 and its associated Bases (I) to be functionally consistent with the TS 3.0.5 statement incorporated in the current staff-approved
Standard Specifications for Westinghous'e
- Plants, NUREG-1431, (2) has no impact on plant equipment or its operation; and (3) clarifies that the testing necessary to declare equipment OPERABLE may be completed under administrative controls.
Therefore, the proposed change is acceptable.
3.0 STATE CONSULTATION
In accordance with the 'Commission's regulations, the State of North Carolina official was notified of the proposed issuance of the amendment.
The State official had no comments.
4.0 NVI ON EN AL CONS D RATION The amendment changes a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 and changes the Surveillance Requirements.
The NRC staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released
- offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure.
The Commission has previously issued a
proposed finding that the amendment involves no significant hazards consideration, and there has been no public comment on such finding (62 FR 6569).
Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9).
Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the 'amendment.
- 5. 0 CONCLUSION The Commission has concluded, based on the considerations discussed
- above, that:
(1) there is reasonable assurance'that the heal'th and safety of the public will not be endangered by operation in the proposed
- manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor:
N. B.
Le Date:
Parch 17, 1997
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