View source for A05106, Documents That SPDS at Plant Declared Fully Operational on 870324 After Successfully Completing Various Tests & Operator Training,Per NRC 850727 Order Confirming Util Commitments Re Implementation of Suppl 1 to NUREG-0737

{{Adams
| number = ML20214S932
| issue date = 06/01/1987
| title = Documents That SPDS at Plant Declared Fully Operational on 870324 After Successfully Completing Various Tests & Operator Training,Per NRC 850727 Order Confirming Util Commitments Re Implementation of Suppl 1 to NUREG-0737
| author name = Mroczka E
| author affiliation = NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES
| addressee name = 
| addressee affiliation = NRC OFFICE OF ADMINISTRATION &amp; RESOURCES MANAGEMENT (ARM)
| docket = 05000336
| license number = 
| contact person = 
| case reference number = RTR-NUREG-0737, RTR-NUREG-737, TASK-1.D.2, TASK-TM
| document report number = A05106, A06369, A5106, A6369, TAC-51257, NUDOCS 8706100058
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE, UTILITY TO NRC
| page count = 2
| project = TAC:51257
| stage = Other
}}

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HARTFORD. CONNECTICUT 06141-0270 L   L     J Z Z '' C '5 ",                                                  (203) 665-5000 June 1,1987 Docket No. 50-336 A05106 AC6369 Re: Supplement I to NUREG-0737 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555 Gentlemen:
Millstone Nuclear Power Station, Unit No. 2 Supplement I to NUREG-0737 Safety Parameter Display System In a {{letter dated|date=July 27, 1985|text=letter dated July 27, 1985}},(1) the NRC Staff issued an Order confirming various commitments made by Northeast Nuclear Energy Company (NNECO) on behalf of Millstone Unit No. 2 regarding the implementation of Supplement I to NUREG-0737. In particular, the Confirmatory Order specified that the Safety Parameter Display System (SPDS) at Millstone Unit No, 2 be fully operational with the operators trained " prior to the start of Cycle 8 or by March 25,1987, whichever is later." The purpose of this letter is to document that the SPDS at Millstone Unit No. 2 was declared fully operational on March 24,1987 af ter successfully completing various tests and operator training. This is in full accord with the license condition as transmitted in Reference (1).
In a {{letter dated|date=February 12, 1987|text=letter dated February 12, 1987}},(2) the NRC Staff issued a Safety Evaluation (SE) for the SPDS at Millstone Unit No. 2. NNECO has reviewed the SE and offers the following comments for the purpose of clarification and accuracy:
: 1.      A revision of Emergency Operating Procedure safety function check sheets at Milistone Unit No. 2 reflected the fact that containment temperature is no longcr used by the operators to determine the status of the containment integrity safety function. Accordingly, containment temperature has been removed from the SPDS containment integrity algorithms. Containment temperature sensors are connected to the integrated computer system (ICS), the values undergo signal validation, and the resultant information can be accessed from any ICS terminal.
(1)      E. 3. Butcher letter to 3. F. Opeka, dated July 27,1985, " Order Modifying License Confirming Additional Licensee Commitments on Emergency Response Capability (Supplement I to NUREG-0737)."
(2)      D. H. Jaffe letter to E. 3. Mroczka, dated February 12,1987, " Safety Evaluation, Safety Parameter Display System (TMiltem I.D.2)."
0 0 8706100058          870601
                                          ~
DR ADOCK 05000336 PDR          .

U.S. Nuclear Regulatory Commission
,, *' "A06369/Page 2 June 1,1987
: 2. The third sentence of the second paragraph on page 5 of the Staff SE should read, "The sensor signal is given. . .", as opposed to "The variable is given. . .".
: 3. The sensor signal clipping algorithm provided by the ICS vendor invalidates the meaning of range checking. The signal clipping matter is presently being resolved. For the present, the "R" quality tag is not being used.
Thus, sensor data is either good (blank) or bad (X or S). This situation is being remedied and is more conservative than what is stated in the Safety Analysis Report since the data which would have qualified for an "R" designation are being categorized as " bad"(X or S).
: 4. The El analog isolators utilize a Burr-Brown " transformed coupled isolation amplifier", not an " optical isolator" as stated (sce page 7, Section 3.7, paragraph 3).
: 5. The SE states that the maximum credible fault (MCF) voltage and potential current were 120 VAC and 125 VDC, both at 20 amperes. Since the instrumentation cables are separated from all high voltage cables at Millstone Unit No. 2, the MCF voltage was determined to be 120 VAC and 125 VDC. A MCF current value was not supplied. The Energy Incorporated isolators were tested with 140 VAC and 140 VDC applied to the output in the transverse mode with the test source fused at 20 amperes. During the application of the test voltage, the current peaked at 240 amperes on the A.C. test and 250 amperes on the D.C. test. There was no measurable effect on the isolators input as monitored with a digital storage oscilloscope. This specific information was provided to lette s dated October 24,1986l3) and November 17,1986.(the 4/    NRC Staff in If you have any questions, please contact us.
Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY 28 )
E. 3/41roczka #
Senior Vice President cc:    W. T. Russell, Region 1 Administrator D. H. Jaffe, NRC Project Manager, Millstone Unit No. 2 T. Rebelowski, Resident Inspector, Millstone Unit No. 2 (3)    3. F. Opeka letter to A. C. Thadani, dated October 24,15 36, " Safety Parameters Display System."
(4)    3. F. Opeka letter to A. C. Thadani, dated November 17,1986, " Safety Parameters Display System."
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