ML20117C332
Text
_
juN 141983
/
Docket Nos. 50-272 50-311 MEMORANDUM FOR:
Darrell G. Eisenhut, Director of Licensing, NRR FROM:
Richard W. Starostecki, Director, Division of Project and Resident Programs
SUBJECT:
NUREG-0737, TECHNICAL SPECIFICATIONS (GENERIC LETTER 82-16)
REVIEWS FOR SALEM UNITS 1 AND 2 Region I has reviewed the Salem Units 1 and 2 Technical Specifications to determine if they were consistent with the guidance of Generic Letter No.
82-16. represents a status summary for each of the items. As noted, except for the incorporation of Technical Specifications to Limit Over-time (I.A.1.3) and reporting of safety and relief valve challenges (II.K.3.3),
all items have been satisfactorily completed.
For these remaining two items, the licensee has indicated that an amendment request to incorporate these items as well as other organizational changes is scheduled for submittal in June 1983. The NRR project manager has indicated that he will followup on these items when the amendment request is received.
Additionally, during our review, some discrepancies were noted between the Unit 1 and 2 TS related to Auxiliary Feedwater automatic initiation and flow indication. These deficiencies, which are delineated in the enclosure, should be brought to the licensee's attention for resolution.
This action completes work to be performed by Region I under TAC #49754 and #49755 which includes 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> by the Region I technical staff.
Original Signed Br.:
Richard W. Starostecki, Director Division of Project and Resident Programs
Enclosures:
Status Summary of NUREG-0737 Technical Specifications cc w/encls:
G. Lainas, AD/0R, NRR S. Varga, NRR D. Fischer, NRR J. Thoma, TA, AD/0R, NRR E. Greenman, RI 8505090390 841002 L. Norrholm, RI PDR FOIA W. Lazarus, RI BAR FIEL84-616 PDR D. Haverkamp, RI P. Erickson, NRR J. Zwolinski, NRR C TACT:
R. Jacobs A,
/ \\t DPRPk'[s@DPRP l b3 8-488-122 U
g P G".y DPR Jac
,)m Laz Greenman Starostec i g-
i i
ENCLOSURE I STATUS
SUMMARY
OF NUREG-0737 TECHNICAL SPECIFICATIONS (GENERIC LETTER 82-16) FOR SALEM UNITS 1 AND 2 1.
STA Training (I.A.1.1.3)
Amendment No. 46 on Unit 1 and Amendment II on Unit 2 dated September 7, 1982, incorporated TSs that specified the qualifications, training, and on duty requirements for STAS, consistent with the guidelines of NUREG-0737, Item I.A.1.3.
2.
Limit Overtime (I.A.1.2)
By letter dated December 29, 1982, the licensee indicated that they would submit an amendment request for this item when they submitted an amendment request involving numerous revisions to Section 6 of the T.S.
By phone conversation on May 27, 1983. The licensee indicated that this amendment request is scheduled for submittal to the NRC in June 1983.
3.
Short Term Auxiliary Feedwater System Evaluation (II.E.1.1)
Amendment No. 39 on Unit I dated March 21, 1981 and the original license on Unit 2, incorporated TSs that specified the means to maintain the AFW redundancy necessary to assure adequate AFW flow for normal transient and accident conditions.
4.
Safety Grade AFW System Initiation and Flow Indication (II.E.1.2)
Amendment No. 39 on Unit I dated March 21, 1981 and the original TS on Unit 2, incorporated TSs specifying the operability of automatic ini-t1ation and flow indication.
In response to an NRC request dated December 22, 1982, the licensee by letter dated March 28, 1983, submitted an amendment request to add manual initiation of AFW pumps to the list of functional units that initiate the AFWS for both Units 1 and 2. This amendment has not yet been processed, but the NRR project manager in-dicated that NRR would perform the review of that amendment.
'During our review, some discrepancies were noted between Unit I and 2 TSs which should be rectified. Unit 2 TS Table 3.3-11, Accident Monitoring Instrumentation, under Item 11, Auxiliary Feedwater Flow Rate, indicates I channel for both the required and minimum number of channels. Unit 1 TS Table 3.3-11a under Auxiliary Feedwater Flow Rate, indicates 4 (1/ steam generator) for required and 3 (1/ steam generator) for the minimum number of channels. Since both units, have 4 feedwater flow indications, 1 per steam generator, the Unit 2 TS are ambiguous and should be modified to be the same as Unit 1.
Similarly, on Unit 2, TS Table 3.3-3, Item 8c con-cerns automatic initiation of auxiliary feedwater pumps on emergency trip of steam generator feed pumps. This TS is only applicable during Mode 1.
However, the similar TS on Unit 2, (i.e. TS Table 3.3-3 Item 8e) is applicable during Modes 1 and 2. The reason for this discrepancy is not apparent. Westinghouse model TS indicates Modes 1 and 2 for this TS.
I
5.
Dedicated Hydrogen Penetrations (II.E.4.1)
Both Units 1 and 2 have internal recombiners. Hence, this NUREG-0737 f tem is not applicable.
6.
Containment Pressure Setpoint (II.E.4.2.5)
Amendment No. 37 dated July 30, 1981 on Unit 2 revised the containment pressure setpoint to less than or equal to 4.0 psig in accordance with this Action plan item. This setpoint was also incorporated in the original TS for Unit 2.
7.
Containment Purge Valve (II.E.4.2.6)
Amendment No. 41 on Unit 1 and Amendment No. 7 on Unit 2 dated April 19, 1982 incorporated requirements that the purge valves be locked shut in Modes 1, 2, 3, and 4, be verified locked shut every 31 days, and esta-blished test requirements on these valves to ensure that there is no excessive degradation of valve seats.
8 Radiation Signal on Purge Valves (II.E.4.2.7)
The original TS on both units incorporated a purge valve closure signal on sensing high radiation in the Containment.
Amendment No. 41 on Unit I and No. 7 on Unit 2 specify that the purge valves may only be used in Modes 5 and 6.
- 12. Reporting SV and RV Failures and Challenges (II.K.3.3)
There are no TS incorporated on either Unit 1 or 2 to specifically require reporting of safety valve (SV) and relief valve (RV) failures and chal-lenges. The licensee in his letter dated December 29, 1982 in response to Generic Letter 82-16 did not identify this as an area where specific TSs were needed. By phone conversation on May 27, 1983 with Mr. E. Liden of PSE&G, the licensee agreed to include specific reporting requirements in an amendment request for revising Section 6 of the TS. The licensee indicated that this amendment request is scheduled for submittal in June
-1983.
- 13. Anticipatory Trip on Turbine Trip (II.K.3.12)
An anticipatory reactor trip on a turbine trip is included in the original Westinghouse design and is incorporated in the original TS on both plants.
-