ML17158A238
| ML17158A238 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 04/15/1994 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17158A237 | List: |
| References | |
| GL-88-01, GL-88-1, NUDOCS 9404250052 | |
| Download: ML17158A238 (5) | |
Text
~>5 Ae0, Wp O~
A0O
'+n qO
++*<<+
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, O.C. '20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO.
TO FACILITY OPERATING LICENSE NO.
NPF-14 AMENDMENT N0.104 TO FACILITY OPERATING LICENSE NO. NPF-22 PENNSYLVANIA POWER
& LIGHT COMPANY ALL GHENY ELECTRIC COOPERATIVE INC.
SUS UEHANNA STEAM ELECTRIC STATION UNITS 1
AND 2 DOCKET NOS. 50-387 AND 50-388
1.0 INTRODUCTION
By letter dated April 16, 1993, the Pennsylvania Power and Light Company (PP&L or the licensee) submitted a request for changes to the Susquehanna Steam Electric Station, Units 1 and 2, Technical Specifications (TS).
The requested changes would revise the TSs to conform to the NRC staff positions on Inservice Inspection (ISI) and on monitoring of unidentified leakage as set forth in Generic Letter (GL), 88-01, NRC Position On Intergranular Stress Corrosion Cracking (IGSCC) In Austenitic Stainless Steel Piping.
1 2.0 DISCUSSION I
NRC GL 88-01, issued January 25, 1988, provided guidance in the form of NRC positions regarding Intergranular Stress Corrosion Cracking (IGSCC) problems in Boiling Water Reactor (BWR) piping made of austenitic stainless steel that is 4 inches or larger in nominal diameter and contains reactor coolant at a
temperature above 200 degrees F during reactor power operation regardless of ASME Code classification.
NRC GL 88-01 requested licensees of operating BWRs and holders of construction permits for BWRs to provide information regarding conformance with the NRC positions.
Two of the items which the GL requested licensees to address were:
(1) a TS change to include a statement in the TS section on Inservice Inspection (ISI) that the ISI program for piping covered by the scope of NRC GL 88-01 will be in conformance with the NRC positions on
- schedule, methods and personnel, and sample expansion included in the GL, and (2) confirmation of the licensee's plans to ensure that the TSs related to leak detection will be in conformance with the NRC positions on leak detection included in the GL.
The NRC position on leakage detection specifically stated that unidentified leakage be limited to an increase of 2 gpm over a 24-hour period.
3.0 EVALUATION The NRC previously completed an evaluation of PP&L's programs to meet the 13 staff positions and other guidance i.n GL 88-01.
4404250052 940415 PDR ADOCK 05000387 P,
~
By letter dated February 16,
- 1990, the staff informed PP&L that their programs were fully acceptable and satisfied all of the requirements in GL 88-01 except for the TSs on ISI and unidentified leakage and their position concerning crack evaluation.
The latter issue was subsequently resolved.
The licensee has proposed the following changes to the TSs in conformance with the guidance in GL 88-01:
l.
Add new Surveillance Requirement 4.0.5.f to read "The Inservice Inspection (ISI) Program for piping identified in NRC Generic Letter 88-01 shall be performed in accordance with the staff position o'
- schedule, methods and personnel, and sample expansion included in the Generic Letter".
2.
Revise the Limiting Condition for Operation (LCO) in Section 3.4.3.2e to require that reactor coolant system leakage shall be limited to a
2 gpm increase in unidentified leakage within any 24-hour period in Operational Condition 1'.
The current requirement is a 2 gpm increase in unidentified leakage within any 4-hour period.
3.
Modify ACTION requirement e for the above LCO to specify that:
e.
With any reactor coolant system UNIDENTIFIED LEAKAGE increase greater than 2 gpm within any 24-hour period, in OPERATIONAL CONDITION 1 only, identify the source of leakage increase as not service sensitive Type 304 or 316 austenitic stainless steel within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 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 SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
The 'revisions limit the increase to 2 gpm within any 24-hour period vs the present 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, specify that this requirement only applies while the units are at power (Operational Condition 1) and allow 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> to try to identify the source of the unidentified leakage.
4.
Modify ACTION requirement
- a. in Section 3.4.3. 1 on Leakage Detection Systems to read:
a.
With one or both channels of the drywell floor drain sump level monitoring system inoperable, operation may continue for up to 30 days provided the drywell floor drain sump flow rate=is monitored and determined by alternate means at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
Otherwise, 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 followin 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
g The above conforms to staff position (3) in Supplement 1 to GL 88-01.
5.
Modify SURVEILLANCE RE(UIREMENT 4.4.3.2. lb to require that the drywell floor drain sump level be monitored every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> vs the 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> in the current TS.
This is in conformance with staff position (1) in Supplement 1 to GL 88-01.
6.
Modify the BASES in 3/4.4.3.2 on OPERATIONAL LEAKAGE by adding the sentence:
"The limit of unidentified leakage has been changed to reflect the requirements of Generic Letter 88-01".
The above changes to the TSs are in accordance with the staff positions and model TSs in GL 88-01 and Supplement 1 to GL 88-01 and are acceptable.
4.0 STATE CONSULTATION
In accordance with the Commission's regulations, the Pennsylvania State official was notified of the proposed issuance of the amendments.
The State official had no comments.
- 5. 0 ENVIRONMENTAL CONSIDERATION The amendments change a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20.
The NRC staff has determined that the amendments involve 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 s.ignificant increase in individual or cumulative occupational radiation exposure.
The Commission has previously issued a proposed finding that the amendments involve no significant hazards consideration, and there has been no public comment on such finding (58 FR 28058).
Accordingly, the amendments meet eligibilitycriteria 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 amendments.
6.0 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 amendments will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor:
R. Clark pate'pril 15, 1994.
EC P
F E