ML17058B757
| ML17058B757 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 05/10/1993 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17058B756 | List: |
| References | |
| NUDOCS 9305200088 | |
| Download: ML17058B757 (8) | |
Text
~p,8 RE0y, (4
Mp0 Cy A,n0
++*+~
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON. D.C. 20555.0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 40 TO FACILITY OPERATING LICENSE NO. NPF-69 NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT NUCLEAR STATION UNIT 2 DOCKET NO. 50-410
- 1. 0 INTRODUCTION By letter dated February 12, 1993, Niagara Mohawk Power Corporation (NHPC or the licensee) submitted a request for changes to the Nine Mile Point Nuclear
- Station, Unit 2, (NHP-2) Technical Specifications (TS).
The requested changes would revise a footnote in TS Table 1.2, "Operational Conditions,"
and the Applicability statement of TS 3/4.9.1, "Reactor Mode Switch."
The TS currently permit withdrawal of a single control rod in the Hot or Cold Shutdown Conditions for the purpose of recoupling a control rod to its drive.
This is done by placing the mode switch in the Refuel position, provided the one-rod-out interlock (which limits withdrawal to one rod) is operable.
Permission for this withdrawal for recoupling is provided in a footnote to the Conditions 3 and 4 mode switch position requirement statements in TS Table 1.2.
The licensee has proposed that the word "recoupled" in this footnote be replaced with "moved."
This change would provide permission for the movement of a single control rod in those operational conditions for purposes other than recoupling, e.g., for post-scram venting, friction testing, or scram time testing.
There is currently no TS required surveillance related to the rod withdrawal for recoupling permitted for Conditions 3 and 4 in Table 1.2.
The licensee proposes to augment the Applicability statement of TS 3/4.9. 1 to include "Operational Conditions 3 and 4 when the reactor mode switch is in the Refuel position."
This change would extend the applicability of the appropriate testing requirements for the one-rod-out interlock to Operational Conditions 3
and 4 when the reactor mode switch is in the Refuel position.
2.0 EVALUATION The NRC staff has evaluated NHPC's submittal dated February 12,
- 1993, considering the factors that are discussed below.
The proposed change to TS Table 1.2 is similar to existing approved TS Table 1.2 specifications in other BWR reactors (e.g., Clinton, Grand Gulf, LaSalle,
- Perry, and River Bend).
These were either in the initial TS or the result of approved changes similar to those proposed by NHPC.
9305200088 5000yg0 P30510 pDR ADQCH, 05 pDR
~r
Since control rod movement is blocked when the mode switch is in the Shutdown
- position, movement of the switch to Refuel (or to Startup or Run) is necessary to move a rod for recoupling or any other purpose.
When the mode switch is in the Refuel position, the redundant logic of the one-rod-out interlock limits rod movement to one rod.
Because of the required shutdown margin with one control rod fully withdrawn, there is reasonable assurance that the reactor will remain subcritical with the mode switch in the Refuel position.
The proposed change to TS Table 1.2 does not change the current permission to withdraw a single control rod in Operational Conditions 3 and 4, but it does expand the permitted testing and maintenance activities for withdrawal.
While this will increase the frequency of single control rod withdrawals in Operational Conditions 3 and 4, the probability of withdrawal events is not affected since these events would occur in Operational Conditions 1,
2, or 5.
Haintenance and testing on control rod drives are currently allowed for all BWRs in Operational Conditions 1 and 2 (Startup and Power Operation, respectively),
where these activities are not under the control of the'one-rod-out interlock, as well as in Operational Condition 5 (Refueling).
The proposed change to TS 3/4.9. 1 provides appropriate surveillance of the one-rod-out interlock in Operational Conditions 3 and 4, as it currently does for Operational Condition 5.
The factors discussed above indicate that the proposed change to TS Table 1 '
is consistent with previous NRC staff approvals and existing TS for other BWR
- reactors, provides for needed maintenance and testing of rods, is not significantly different from currently permitted rod withdrawal operations, and does not increase the probability of a rod withdrawal event.
The proposed change to TS 3/4.9. 1 provides additional and appropriate surveillance requirements for rod withdrawal in Operational Conditions 3 and 4 not currently required for permitted withdrawals for control rod recoupling.
Therefore, the staff concludes that the proposed changes to the NHP-2 TS are acceptable,
3.0 STATE CONSULTATION
In accordance with the Commission's regulations, the New York State official was notified of the proposed issuance of the amendment.
The State official had no comments.
- 4. 0 ENVIRONMENTAL CONSIDERATION 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 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 (58 FR 16866).
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 health 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:
John E. Menning Date:
May 10, 1993
y) ss Docket No. 50-410 Hr. B. Ralph Sylvia Executive Vice President, Nuclear Niagara Mohawk Power Corporation 301 Plainfield Road
- Syracuse, New York 13212 May 10, 1993
Dear Hr. Sylvia:
SUBJECT:
ISSUANCE OF AMENDMENT FOR NINE MILE POINT NUCLEAR STATION, UNIT 2 (TAC NO. H85888)
The Commission has issued the enclosed Amendment No. 40 to Facility Operating License No.
NPF-69 for the Nine Mile Point Nuclear Station, Unit 2.
The amendment consists of changes to the Technical Specifications in response to your application transmitted by letter dated February 12, 1993.,
The amendment revises Technical Specifications (TS) Table 1.2, "Operational Conditions,"
and Section 3/4.9. 1, "Reactor Mode Switch," to permit movement of a single control rod with the reactor in the Hot Shutdown or Cold Shutdown Conditions for post-maintenance and surveillance testing on control rod drives.
The TS had previously permitted movement of a control rod in these operational conditions to recouple a control rod to its drive.
A copy of the related Safety Evaluation is enclosed.
A Notice of Issuance will be included in the Commission's next regular biweekly Federal Re<eister notice.
Enclosures:
1.
Amendment No. 40 to NPF-69 2.
Safety Evaluation cc w/enclosures:
See next a
e Sincerely, Original Signed By:
John E. Henning, Project Manager Project Directorate I-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation OFFICE PDI-1:LA PDI-1: PH SRXB 0
PDI-1:D NAME CVo an g)
JNennin 5vl RJOIIes 4AV$N>~F RACa ra DATE 0/'Z~/93 lt al 93 93 5 J 93 5'0 93 OFFICIAL RECORD COPY FILENAME: G: 'ikNMP2iNM285888. AMD
f,y) l,
-1
\\