ML20247R746
| ML20247R746 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 05/31/1989 |
| From: | POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK |
| To: | |
| Shared Package | |
| ML20247R733 | List: |
| References | |
| JPTS-80-011, JPTS-80-11, NUDOCS 8906070303 | |
| Download: ML20247R746 (40) | |
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PROPOSED TECHNICAL SPECIFICATION CHANGES -
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REGARDING LOW PRESSURE COOLANT INJECTION y(
PUMP FLOW SURVBLLANCE AND p.
DEMONSTRATE / VERIFY TERMINOLOGY (JPTS-80-011) i
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l' NEW YORK POWER AUTHORITY James A. FitzPatrick Nuclear Power Plant i
Docket 50-333 '
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Attachrr.snt 11 NEW YORK POWER AUTHORITY James A. FitzPatrick Nuclear Power Plant Docket 50-333 Safety Evaluation for Technical Specification Changes Regarding Low Pressure Coolant injection Pump l
Flow Surveillance and Demonstrate / Verify Terminology 1.
DESCRIPTION OF THE PROPOSED CHANGES This application proposes to revise the James A. FitzPatrick Nuclear Power Plant Technical SpecUications to incorporate two distinct changes:
1.
The minimum allowable Low Pressure Coolant injection (LPCI) pump ficw is changed to reflect the loop-selection-logic modifications installed during the Cycle 1/ Reload 2 refueling outage. Other changes reflect the division of the LPCI system into two subsystems.
2.
Improve consistency with accepted, existing, operability requirements by repiacing the term " demonstrate" with " verify" where appropriate to eliminate the need for redundant and unnecessary surveillance testing. Other similar changes also clarify surveillance test and operability requirements.
Since these two changes are not directly related, each section of this safety evaluation has been divided into two subsections - one for each change.
- 1. LPCI Pump Flow Surveillance Page 114:
[1a] In Specification 4.5.A.3, the phrase "three RHR pumps" is replaced with the phrase "each RHR pump" the phrase "23,100 gpm" is replaced with the phrase "9,900 gpm" and
- the phrase 'of 20 psig' is replaced with the phrase "to primary containment differential pressure of greater than or equal to 20 psid."
The revised Specification reads as follows. (The revised portions are underlined.
These phrases are not underlined in the actual specification.)
"LPCI System testing shall be as specified in 4.5.A.1e, b, c, d, f and g except that each RHR pump shall deliver at least 9,000 gpm against a system head corresponding to a reactor vessel to primary containment differential pressure of greater than or equal to 20 psid."
[1b]
In Specification 3.5.A.3, the phrase "The LPCI mode" is replaced with the phrase
'Both LPCI subsystems."
[1c]
in Specification 4.5.A.2, the phrase "the LPCI Systems" is replaced with the phrase "both LPCI subsystems."
1-
=#
Attachment ll 4
[1d]
Delete Specification 4.5.A.3.a in its entirety and renumber Specifications 4.5.A.3.b and 4.5.A.3.c as 4.5.A.3.a and 4.5.A.3.b, respectively. Renumbered Specification 4.5.A.3.a is moved from the top of page 115 to the bottom of page 114 and the i
renumbered Specification 4.5.A.3.b is moved to the top of page 115.
Page 115:
[1e]
In Specification 3.5.A.3.b, the phrase "From the time that the LPCI mode" :s replaced with the phrase "From the time that one of the LPCI subsystems."
In Specification 3.5.A.3.b, the phrase "unless the LPCI mode is made operable" is replaced with the phrase "unless that subsystem is made operable."
[1f]
In Specification 3.5.A.3.b, replace the phrasa "these 7 days all active components of both Core Spray Systems and the containment spray subsystem (including two RHR pumps)" with the phrase "these 7 days the operable LPCI subsystem and both Core Spray Systems."
[1g]
In renumbered Specification 4.5.A.3.a, replace the pnrase "When it is determined that the LPCI mode is inoperable, both Core Spray Systems, and the containment spray subsystem" with the phrase "When it is determined that one LPCI subsystem is inoperable, the operable LPCI subsystem and both Core Spray Systems."
Page 115a:
[1h]
In Specification 4.5.B.1, the phrase "LPCI System" is replaced with the phrase "LPCI subsystems."
1 Page 125:
l 1
[11]
In the sixth paragraph of Bases 3.5.A, the sentence:
l "This system is completely independent of the Core Spray System; however it does function in combination with the Core Spray System to prevent excessive fuel clad temperature."
is replaced with the sentence:
"These subsystems are completely independent of the Core Spray System; however, they function in combination with the Core Spray System to i
prevent excessive fuel clad temperature."
i Page 126 and 127:
[1j]
In the second paragraph (on page 126) of Bases 3.5.A, delete the article "a" from the phrase " constitute a 1-out-of-2 systems."
l Replace the paragraph on pages 126 and 127 which currently reads:
j "Should the loss of one RHR pump occur, a nearly full compliment....at least two RHR pumps must be available to fulfill the containment cooling function.
The seven-day repair period is set on this basis."
with the sentence l
l l
M 1 "Similarly, should one LPCI subsystem become inoperable, the remaining LPCI subsystem and the Core Spray System are available to provide core cooling." -
- 2. Demonstrate / Verify Terminology The word " demonstrate" is replaced with the word " verify" (or the appropriate form of verify) as follows:
Page 89:
[2a]
In the first paragraph of Specification 3.3.A.2.a, replace the phrase "and shall not be started unless (1) investigation has demonstrated" with the phrase "and shall not be started unless (1) investigation has shown."
[2b]
In the second paragraph of Specification 3.3.A.2.a, replace the phrase "If investigation demonstrates" with the phrase "If investigation shows."
Page 106:
[2c]
In Specification 4.4.B, replace the word " demonstrated" with the word " verified."
Page 109:
[2d]
in Bases 4.4.B: Delete the phrase "and that reliability is good"; replace the word
" demonstrating" with the word " verifying"; and, replace the word " operation" with the word " operability."
Page 114:
[2e]
In Specification 4.5.A.2, replace the first occurrence of the word " demonstrated" with the word "verifia'J."
[2f]
In Specificaf. 4.5.A.2, replace the second occurrence of the word " demonstrated" with the word " verified."
Page 115:
[2g]
In the renumbered Specification 4.5.A.3.a, replace the word " demonstrated" with the word " verified."
Pages 115a and 116:
(2h]
In Specification 4.5.B.2, replace the word " demonstrated" with the word " verified."
1 In Specification 4.5.B.3. replace the word " demonstrated" with the word " verified."
l Page 118:
[2i]
in Specification 4.5.C.1.a, replace both occurrences of the word " demonstrated" with the word " verified."
l _ _ _ _ - _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _
y Attar nment il Page 120:
[2j]
In Specification 4.5.D.2.a, replace the word " demonstrated" with the word " verified."
[2k]
in Specification 4.5.D.2.b, replace the word " demonstrated" with the word " verified."
Page 121a:
[21]
In Specification 4.5.E.2, replace the word " demonstrated" with " verified."
Page 126:
[2m] In the third paragraph of Bases 3.5.A, replace the phrase " demonstrated to be" with the word " verified."
[2n]
in the third paragraph of Bases 3.5.A, replace the word " demonstration" with the word
" verification." Also, delete the phrase "a manual initiation of."
Page 127:
[2o]
in the second paragraph of Bases 3.5.B. replace the word " demonstrated" with the word " verified."
[2p]
In the second paragraph of Bases 3.5.B, delete the phrase "which is tested daily" and combine the last two sentences into a single sentence. The new last sentence becomes:
" Based on the fact that when one containment cooling subsystem becomes inoperab!e only one systems remains, a seven-day repair period was specified."
f Page 129:
l
[2q)
In Bases 3.5.E, replace the word " demonstrations" with the word " verifications."
Page 132:
[2r]
In the third paragraph of Bases 4.5, replace the word " demonstrating" with the word
" verifying."
l In the third paragraph of Bases 4.5, replace the last four sentences with the sentence:
" Consistent with the definition of operable in Section 4.0.C, demonstrate means conduct a test to show; verify means that the associated surveillance activities have been satisfactorily performed within the specified time interval."
Page 145c:
1
[2s]
In Specification 3.6.l.2.c, replace the word " demonstrate" with the word "show."
l j
Page 156:
[2t]
in Bases 3.6 and 4.6,Section I, replace the word " demonstrate" with the word "show."
l l a
o ~
Attachment ll '
Page 183:
[2u) in Specification 4.7.B.2, replace the word " demonstrated" with the word " verified."
Page 218:
[2v)
In Specification 4.9.B.6, replace the phrase "the availability of the operable off-site sources shall be verified by the correct breaker alignment indicating power availability" with the phrase "the availability of off-site power shall be assured by verifying correct breaker alignment and by verifying that the associated off-site electricalline is energized."
Page 239:
[2w)
In Specification 4.11.B, replace the phrase
- checked for operability" with the phrase
" demonstrated operable."
[2x) - In Specification 4.11.C, replace the phrase " checked for operability" with the phrase
" demonstrated operable."
[2y]
In Specification 4.11.C.1, replace the phrase " checked for operability" with the phrase
" verified operable."
Page 241:
[2z) in Specification 3.11.D.2, replace the phrase:
"provided that: the operable Emergency Diesel Generator System and all its emergency loads be demonstrated to be operable immediately and daily thereafter."
with the phrase:
"provided that:
- the operable Emergency Diesel Generator System is demonstrated to be operable immediately and daily thereafter; and, all Emergency Diesel Generator System emergency loads are verified operable immediately and daily thereafter."
l l
-S-i
+ 1
-l'I. PURPOSE OFTHE PROPOSED CHANGES
- 1. LPCI Pump Flow Surveillance
Background
For the first operating cycle, FitzPatrick's LPCI mode of the Residual Heat Removal (RHR) system included four, one-third capacity pumps and loop-selection-logic. During normal operation, the LPCI injection valves were closed and the RHR cross-tie valve was open. See UFSAR Figure 6.4-3.
On receipt of a loss-of-coolant (LOCA) signal, the loop-selection-logic (using a system of l
pressure transducers) would determine in which of the two recirculation loops the break had i
occurred. The injection valve on the broken loop would be closed by this logic and flow from all l
four LPCI pumps would be diverted to the unbroken recirculation loop.
With this arrangement, the worst single failure (failure of a LPCI injection valve to open), would result in core spray being relied upon to cool the core and reflood the vessel. (See Reference 4, Section ll).
1 LPCI Loop-Selection-Logic Modification With the issuance of Appendix K to 10 CFR 50 in 1974, emergency core cooling system i
(ECCS) acceptance criteria became more conservative. As originally designed, FitzPatrick's core sprays, acting alone, could not satisfy this new criteria. To satisfy the new criteria, a plant i
modification was developed that would assure that, even with the single most limiting equipment l
failure (failure of a single LPCl injection valve to open), the flow from two LPCI pumps would bo j
available to reflood the vesselin the event of a LOCA. This modification is sometimes called the Vermont-Yankee fix.
Four basic elements made up the modification. A fifth modification was mandated by the NRC.
These modifications are as follows:
i 1.
The LPCI loop-selection-logic was eliminated. Control logic was modified so both l
LPCI injection valves (10MOV-25A and 10MOV-25B) open on an accident signal.
I 2.
The control logic for both recirculation pump discharge valves was modified so that the valves close on a LOCA signal.
i 3.
The RHR crost tie valves (10MOV-20 and RHR-09) will be locked-closed during normal plant operation.
4.
Flow orifices (RO-107A,107B,107C and 107D) were added to the LPCI pump discharge lines. Since only two pumps will be discharging into a system designed for I
three pumps, this flow resistance was added to prevent the pumps from going into a "run-out" condition and assures adequate NPSH (net positive suction head).
j 5.
Electrical " swing-busses" for LPCI valves were eliminated.
The modification eliminated the LPCI loop-selection-logic and divided the LPCI discharge
' header into two halves, one for each reactor recirculation pump, by closing two valves (10MOV-20 and RHR-09). With this arrangement, two LPCI pumps would discharge into one side of the recirculation system piping through an injection valve downstream of the recirculation pump. In effect, LPCI was divided into two systems, (referred to as subsystems in the Technical Specifications), each with it's own pumps, valves and piping. Even if a single LPCI injection valve fails to open, the flow from two LPCI pumps is still available to reflood the vessel. _ _ - - - - - _ - _ - _ _ _ _.
Attachment il i
' The Authority described the LPCI loop-selection-logic modification in References 4,5 and 7.
l The NRC authorized installation of the LPCI modifications in Amendment 8 (Reference 8). Plant l
operation with these modifications was authorized by the NRC in Amendment 14 (Reference 9).
Operation with independent LPCI valve power supplies was authorized by the NRC in Amendment 30 (Reference 10).
The NRC safety evaluation in Amendment 14 discusses the ECCS performance analysis submitted and concluded that the evaluation was performed in conformance with the l-requirements of 10 CFR 50.46(a).
Technical Specification Changes Page 114: Change [1a]
In Reference 1, the Authority submitted changes to the FitzPatrick Technical Specifications similar to those described in this application. The Authority subsequently withdrew the original (Reference 1) application via Reference 2. Some of the changes proposed in Reference 1 were included in Amendment 98 (Reference 11).
This modification changed the number of pumps on 'each header and added discharge orifices.
(The orifices maintain pump discharge pressure thereby preventing the pump from " running-out.")
Because the LPCI discharge header was effectively split in two, its hydraulic characteristics (primarRy pressure drop), were altered. Consequently, the LPCI pumps will now operate within a different range on their operating curve and the test criteria is revised to reflect this change.
This Technical Specification change increases minimum flow per pump by 2,200 gpm - from 7,700 gpm to 9,900 gpm per pump. No modifications were made to the LPCI pumps themselves.
Rather, Instead of specifying total output flow for the simultaneous operation of three LPCI pumps, the output of each pump is specified.
The change from "psig" to "psid" (pounds per square inch gauge and pounds per square inch differential, respectively) clarifies the basis for the LPCI pump discharge pressure. The change accurately reflects the assumptions in the current reload analysis (Table 4-1, Reference
- 12) and is purely administrative; neither the minimum acceptable test pressure nor the associated test procedure have been altered. This new phraseology more closely adheres to that used in the Standard Technical Specifications and clearly establishes 20 psid as the minimum differential pressure.
Page 114: Changes [1b] and [1c]
Each of these changes reflect the elimination of a "LPCI mode" and the effective division of the LPCI system into two subsystems.
Page 114: Change [1d]
Specification 4.5.A.3.a is deleted because is duplicates the surveillance requirements originally included in Specification 4.5.A.3.b for the modified LPCI system. The surveillance requirements for LPCI were revised to be consistent with the surveillance requirements currently in place for Core Spray (4.5.A.2).
Specification 4.5.A.3.a was originally written assuming that LPCI (RHR) required three of four pumps to fulfill it's intended function. The division of LPCI into two subsystems makes it similar to the Core Spray System - both systems are made up of two subsystems.
7
__-_____a
v 1
- The revised Specification 4.5.A.3.a is similar to the surveillance required by Specification 4.5.A.2 when one Core Spray System is inoperable. Revised Specification 4.5.A.2 requires that "the operable Core Spray System and the LPCI subsystem... be verified operable." Similarly, the revised Specification 4.5.A.3.a requires that "the operable LPCI subsystem and both Core Spray l
Systems" be verified operable when "one LPCI subsystem is inoperable." (See also changes [1g]
and [2g].)
Pages 115 and 115a: Changes [1e], [1f], [1g] and [1h]
Each of these changes reflect the LPCI loop selection-logic modification and the effective division of the LPCI system into two subsystems. These changes also make the LCOs and surveillance requirements for the LPCI system more consistent with those currently in-place for the Core Spray System. Specifications 4.5.A.3.b and 4.5.A.3.c are renumbered 4.5.A.3.a and 4.5.A.3.b respectively, to reflect the deletion of Specification 4.5.A.3.a (change [1d]).
Page 125: Change [11]
l These changes reflect the LPCI loop-selection-logic modification, e.g. elimination of an RHR I
"LPCI mode" and the effective division of the LPCI system into two subsystems.
Pages 126 and 127: Change [1J)
The existing Bases 3.5.A paragraph is not clearly written and doesn't provide any
)
Information not already hcluded in other parts of Bases 3.6. Since the LPCI and Core Spray Systems both provide core cooling, similar logic was applied when the associated LCOs and surveillance requirements were developed. The replacement sentence makes this relationship clear.
Deleting the article "a" will clarify that both the Core Spray and LPCI systems inject water into the core to limit fuel temperatures in the event of a loss of coolant accident.
I
- 2. Demonstrate / Verify Terminology
Background
Changing the word " demonstrate" to " verify" will eliminate the need for redundant and
)
unnecessary surveillance tests performed to satisfying overlapping requirements. These words will make surveillance testing performed to assure equipment opernoility more consistent with the j
Generic Letter (Reference 13) and FitzPatrick's Technical Specifications.
The Authority conducted a review of the FitzPatrick Technical Specifications to identify everywhere " demonstrate" is used. Each occurrence of the word was then reviewed for consistency with this dtfinition. In most cases, no change was necessary.
Where the specification requires demonstration at a specific frequency (i.e. once per cycle, or once per year) or the intent is clearly to require an actual test, no change has been proposed. For example, Specification 4.10.D.1.b requires a shutdown margin demonstration when two control rods are withdrawn from the reactor core for maintenance. Clearly, the intent of this specification is to require a test. The term demonstrate was retained in this instance. Another example is surveillance testing for Emergency Diesel Generators; " demonstrate" was retained in all cases for Emergency Diesel Generator testing. EDG emergency loads are verified operable; see Change
[2z].
i w
Attichment 11 Neither the Standard Technical Specifications nor FitzPatrick Specification 1.0, " Definitions",
explicitly define either " demonstrate" or " verify." However, a definition of an associated term
" operable" was added to Specification 1.0.J (on page 4) as part of Amendment 83 (References 14 and 15). Amendment 83 incorporated the exact definition of operable proposed by the NRC staff in a Generic Letter (Reference 13). Bases 4.0.A through 4.0.D on page 30e (also added as part of Amendment 83) discuss the term operable. Specification 1.0.T defines surveillance frequency.
Specification 4.0.C (page 30) states:
" Performance of a Surveillance Requirement within the specified time interval shall constitute compliance with OPERABILITY requirements for a Limiting Condition for Operation and associated ACTION statements unless otherwise required by the specification..." (Emphasic added.)
Bases 4.0.C (page 30e) states, in part:
"The provisions of this specification set forth the criteria for determination of compliance with the OPERABlUTY requirements of Limiting Conditions for Operation. Under this criteria, equipment, systems or components are assumed to OPERABLE if the associated surveillance activities have been satisfactorily performed within the specified time interval."
implicit in these discussions is the distinction between " demonstrate" and " verify." The Authority has interpreted " demonstrate" to mean " conduct a test to show," while " verify" means "the associated surveillance activities have been satisfactorily performed within the specified time interval." These interpretations are consistent with the NRC staff's guidance, Specification 4.0.C and Bases 4.0.C.
Technical Specification Changes Page 89: Changes [2a] and [2b]
These changes clarify that investigations do not of and by themselves, require a test. An engineering evaluation may be able to " conclusively show" the cause of control rod failure without conducting a special test. " Verify" is not appropriate in this case.
Pages 106 and 109: Changes [2c] and [2d]
These changes will make the surveillance requirements for the Standby Uquid Control System (SLCS) more consistent with the NRC's definition of operable.
Change [2d] also climinates a misleading phrase in Bases 4.4.B (page 109) regarding component reliability. Reliability is based on long-term experience; " good reliability" cannot be determined by a single test. Operability can however, be confirmed with a single test.
Pages 114,115,115a and 116: Changes [2e), [2f], [2g] and [2h]
Each of these changes make the surveillance requirements for the LPCI, containment spray and core spray systems more consistent with the NRC's definition of operable.
Page 118: Change [2i]
I This change makes the action statements for HPCI (High Pressure Coolant injection) inoperability more consistent with the NRC's definition f operable.
.g.
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Attachment ll Page 120: Changes [2j] and [2k)
These changes make the required actions in the event of ADS /SR valve inoperability (ADS logic and HPCI surveillance) more consistent with the NRC's definition of operable.
I Page 121a: Change [21]
This change makes the required actions in the event of RCIC (Reactor Core isolation Cooling) System inoperability (HPCI surveillance) more consistent with the NRC's definition of operable.
l Page 126: Changes [2m] and [2n]
This change makes the terminology used in the Technical Specification Bases 3.5.A more 2
consistent with the terminology in the rest of the Specifications. Change [2n] eliminates a reference to a test ("...a manual initiation...") not consistent with the NRC staff's and FitzPatrick's definition of operable.
Pages 127,129 and 132: Changes [2o], [2p], [2q) and [2r]
These change make the Bases more consistent with Specifications 3.5 and 4.5 and with the NRC's definition of operable. An editorial change [2p] clarifies the basis for a seven-day repair period.
Change [2r] deletes a discussion of the what constitute an appropriate level of surveillance when a component is declared inoperable. This discussion is superseded by the definition of operable in Specification 4.0.C and the corresponding Bases 4.0.A - 4.0.D.
Pages 145c and 156: Changes [2s] and [2t]
This change clarifies that investigations do not, of and by themselves, require a test. An engineering evaluation may be able to " conclusively show" the cause of snubber failure without conducting a special test using only preexisting data. If the evaluation is inconclusive, a test will be performed. " Verify" is not appropriate in this case.
Page 183: Change [2u]
This change makes the required actions in the event of one SBGT (Stand-By Gas Treatment)
System circuit inoperability more consistent with the NRC's definition of operable.
Page 218: Change [2v]
l This editorial change corrects an erroneous implication. As written, this specification incorrectly implies that breaker position alone indicates that off-site power is available. The revised specification makes it clear that in addition to verifying correct breaker position, the associated off-site electrical line must be energized before power can be assured.
Page 239: Changes [2w], [2x] and [2y]
These minor editorial changes eliminate the word " checked," which is undefined, and l
replaces it with more consistent terminology. The intent of this specification is unchanged. i i
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Attrchment ll Page 241: Change [22)
As currertly written, a literal interpretation of Specification 3.11.D.2 require daily tests of both 1
the Emergency Diesel Generator (EDG) and its emergency loads. This literal interpretation is not consistent with the definition of operable and requires unnecessary and excessive testing of EDG emergency loads. Corsistent with current criteria for operability, this change makes it clear that the EDGs are tested (demonstrated) to assure operability, while emergency loads are verified to j
assure operability.
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r Attschment 11 lit. IMPACT OF THE PROPOSED CHANGES
- 1. LPCI Pump Flow Surveillance The technical specification changes proposed by this amendment request reflect the installation of the LPCI-loop-selection modification and the existing plant condition. The changes do not alter the surveillance test procedures used to satisfy these specifications, nor do they reduce the effectiveness of the existing surveillance tests.
The minimum acceptable pump flow is the LPCI pump flow used in recent reload analyses (Reference 16). (See Table 4-1, "Significant input Parameters Used in the FitzPatrick LOCA Analysis," of Attachment IV to Reference 12.) Total LPCI flow to the reactor in the event of LOCA prior to the installation of these modifications was 23,100 gpm (7,700 gpm per pump) with three pump operation. Total flow to the reactor with the modified system is 17,500 gpm assuming two pumps operating into one loop. Total flow to the reactor with two pumps discharging into two loops is 19,800 gpm.
The NRC staff has already reviewed and approved the modifications associated with this change. The NRC authorized installation of the LPCI modifications in Amendment 8 (Reference 8). Plant operation with these modifications was authorized by the NRC in Amendment 14 (Reference 9). Operation with independent LPCI valve power supplies was authorized by the NRC in Amendment 30 (Reference 10).
The Authority recently investigated the potential for deadheading these pumps as a result of pump interaction or miniflow line sizing (References 18,19 and 20). These analyses conclude that pump interaction during miniflow operation is extremely unlikely and that the miniflow lines are adequately sized.
Other LPCI surveillance requirements are not affected by this change. Instrumentation that initiates core cooling systems (including LPCI) in Table 3.2-2 is unchanged. The LPCI cross connect valve position is verified once per cycle (Specification 4.5.A.3.C and Table 4.2-2).
Specification 4.5.G (page 122) requires monthly tests to assure that the LPCI pump discharge lines are filled.
- 2. Demonstrate / Verify Terminology These changes clarify existing Technical Specifications surveillance requirements by making the terminology of the FitzPatrick Technical Specifications more consistent with itself and the NRC's established position on operability (Reference 13).
These changes eliminate need for redundant and unnecessary surveillance tests that result from overlapping requirements. Surveillance test schedules may be revised as a result. Changes to surveillance test procedures may be required to efficiently incorporate the revised schedules but the changes will not reduce the effectiveness of the tests. These changes are consistent with l
the Authority's interpretation of the reworded specifications. The changes do not involve a modification to any structure, system or component.
The surveillance test to assure availability of off-site electrical power in Specification 4.9.B.6 has been improved. In addition to preserving the existing breaker position check, the rewritten specification now specifically requires that the off-site electrical line must be checked to assure that it is energized. No new instrumentation is necessary to perform this surveillance. Minor changes to the associated procedures may be required to incorporate this addition. !
1 Attachment il I'V. EVALUATION OF SIGNIFICANT HAZARDS CONSIDERATION
- 1. LPCI Pump Flow Surveillance in the April 6,1983 FEDERAL REGISTER (48 FR 14870), the NRC published examples of license Amendments that are not likely to involve significant hazards considerations. Example number (vii) of that list is similar to these proposed changes and states:
"A change to make a license conform to changes in regulations, where the license results in very minor changes to facility operations clearly in keeping with the regulations."
Operation of the FitzPatrick Plant in accordance with the proposed Amendment would not involve a significant hazards consideration as defined in 10 CFR 50.92 since it would not:
1.
Involve a significant increase in the probability or consequences of an accident previously evaluated because the technical specification changes are administrative in nature.
The new minimum allowable LPCI (RHR) pump flows are the same values used in the current licensing reload analyses. No accidents as analyzed in the FSAR are adversely affected by these changes.
The LPCI modifications associated with these changes improved the overall reliability of the LPCI system. These changes update plant modifications that have already been reviewed and approved by the NRC in Operating Ucense Amendments 8,14 and 30.
2.
Create the possibility of a new or different kind of accident from any accident previously evaluated because the changes are administrative in nature. The minimum LPCI pump flows proposed in this application are the same as used in recent licensing reload analyses. LPCI's ability to mitigate a loss of coolant accident has been improved through the elimination of the most limiting equipment failure.
3.
Involve a significant reduction in a margin of safety because the changes are administrative. Analyses reviewed and approved by the NRC clearly show that the associated LPCI loop-selection-logic modification improve LPCls ability to perform its intended function and therefore the margin of safety.
- 2. Demonstrate / Verify Terminology Example number (i) of the list published in the April 6,1983 FEDERAL REGISTER, is similar to these proposed changes and states:
l "A purely administrative change to the technical specifications: for example, a change to achieve consistency throughout the technical specifications, correction of an error, or a change in nomenclature."
Operation of the FitzPatrick Plant in accordance with the proposed Amendment would not l
involve a significant hazards consideration as defined in 10 CFR 50.92 since it would not:
1 1.
Involve a significant increase in the probability or consequences cf an accident previously evaluated. This change is administrative in nature: it improves consistency within the Technical Specifications and with the NRC established l
positions on equipment operability. No accidents as analyzed in the FSAR are l
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adversely affected by these changes since these changes do not involve a modification to the plant or Operating Procedures.
The effectiveness of surveillance testing has not been reduced by these changes.
The actual reduction in test frequency is not significant. Verification is adequate to assure that the system is capable of performing its intended function. Less frequent tests will reduce wear and tear on components and will reduce the probability of Inadvertently leaving the tested system misaligned.
j 2.
Create the possibility of a new or different kind of accident from any accident j
previously evaluated because the change is administrative. No modifications to the structures, systems or components are associated with these changes. Minor changes to plant operating procedures may be required to reflect this definition of operable.
3.
Involve a significant reduction in a margin of safety because no modifications to any plant structures, systems or components are associated with these changes. Minor changes to plant operating procedures may be required to reflect this definition of operable.
i 1
i 14-l
t e 1 V.
IMPLEMENTATION OF THE PROPOSED CHANGE l
Implementation of the proposed changes will not impact the ALARA or Fire Protection l
Programs at RtzPatrick, nor will the changes impact the environment.
VI. CONCLUSION The changes, as proposed, does not constitute an unreviewed safety question as defined in 10 CFR 50.59, that is it:
a.
will not increase the probability of occurrence or the consequences of an accident or malfunction of equipment important to safety previously evaluated in the safety analysis report; b.
will not increase the possibility of an accident or malfunction of a different type than any evaluated previously in the safety analysis report; c.
will not reduce the margin of safety as defined in the basis for any technical specification; and e.
involves no significant hazards consideration, as defined in 10 CFR 50.92.. _ _ _ -
J r
Attachment il A
Vil. REFERENCES AND NOTES 1.
PASNY letter, J. P. Bayne to T. A. Ippolito, dated January 6,1981, (JPN-81-003), regarding proposed miscellaneous changes to the Technical Specifications.
2.
NYPA letter, J. C. Brons to D. R. Muller, dated December 24,1985, (JPN-85-092), regarding proposed miscellaneous Technical Specifications.
3.
NYPA letter, W. Fernandez to NRC, dated fWarch 20,1989, (JAFP-89-0214), responds to NRC Region i inspection Report 50-333/88-29.
4.
PASNY letter, G. T. Berry to R. A. Purple, dated July 24,1975 regarding low pressure coolant injection modification. Includes General Electric Report " Emergency Core Cooling Systems LPCIS Modifications for Performance improvement," and pages 67,69,70,79, 132,155 and 156 of FitzPatrick Technical Specifications to illustrate changes.
5.
PASNY letter, G. T. Berry to R. W. Reid, dated December 18,1975 regarding ECCS Appendix K Analysis. Transmits analysis using Dec.1974 interpretation of Appendix K to 10 CFR 50 and include LPCI modification and a plugged core plate.
6.
NRC letter, R. W. Reid to G. T. Berry, dated January 8,1976. Request for additional information regarding LPCI modification submitted July 24,1975.
7.
PASNY letter, G. T. Berry to R. W. Reid, regarding LPCI valves power supply modification.
Transmits preliminary design of the power supply.
l 8.
NRC letter, R. W. Reid to G. T. Berry, dated January 15,1976 issues Amendment 8 to FitzPatrick Operating Ucense. Authorizes installation of LPCI modifications.
9.
NRC letter, R. W. Reid to G. T. Berry, dated March 12,1976 issues Amendment 14 to FitzPatrick Operating Ucense. Authorizes plant operation with LPCI modifications authorized by Amendment 8.
10.
NRC letter, R. W. Reid to G. T. Berry, dated September 16,1977 issues Amendment 30 authorizing plant operation with independent power supplies for LPCI motor-operated valves.
11.
NRC letter, H. l. Abelson to J. C. Brons, dated May 6,1986 issues Amendment 98 to James A. FitzPatrick Nuclear Power Plant Technical Specifications. Permits reactor operation with I
one recirculation loop out of service and includes SIL 380 recommendations on thermal-hydraulic stability.
12.
NYPA letter, J. C. Brons to D. R. Muller, dated December 23,1986 (JPN-86-063) regarding proposed changes to the technical specifications regarding reload 7/ cycle 8 (JPTS-86-023).
Attachment IV is " James A. FitzPatrick Nuclear Power Plant SAFER /GESTR - LOCA Loss-l of-Coolant Analysis," General Electric Co., NEDC-31317P, proprietary version.
13.
NRC letter, D. G. Eisenhut to All Power Reactor Ucensees, dated April 10,1980 regarding the term operable.
14.
PASNY letter, J. P. Bayne to T. A. Ippolito, dated February 20,1981 (JPN-81-14) regarding proposed technical specification change accruing from the NRC staff's clarification of the l
term operable.
15.
NRC letter, H. l. Abelson to J. P. Bayne, dated August 28,1984 issues Amendment 83 to the FitzPatrick Operating Ucense in response to PASNY's Feb. 20,1981 request.
16.
NYPA letter, J. C. Brons to NRC, dated July 29,1988 (JPN-88-037) transmits Reload 8/ Cycle 9 ECCS licensing analysis and associated technical specification changes (JPTS-88-016).
j u
d
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.. ~
. 17.
NRC Bulletin No. 88-04, " Potential Safety-Related Pump Loss," dated May 5,1988.
18.
NYPA letter, J. C. Brons to NRC, dated July 22,1988 (JPN-88-036). Responds to NRC Bulletin No. 88-04.
19.
NYPA letter, J. C. Brons to NRC, dated November 9,1988 (JPN-88-059). Supplemental response to NRC Bulletin No. 88-04 for RHR pumps.
20.
NYPA letter, J. C. Brons to NRC, dated March 6,1989 (JPN-89-009). Supplemental response to NRC Bulletin No. 8841 for: core spray, HPCI, ESW, RHRSW, RHR holding, core spray holding and RCIC pumps.
21.
James A. FitzPatrick Nuclear Power Plant Updated Final Safety Analysis Report (FSAR)
Sections: 6.4.4 " Low Pressure Coolant Injection System;" 6.5.2.5 " Low Pressure Coolant Injection;"
22.
USAEC " Safety Evaluation of the James A. FitzPatrick Nuclear Power Plant," Directorate of Ucensing, issued November 20,1972.
23.
USAEC " Supplement 1 to the Safety Evaluation of the James A. FitzPatrick Nuclear Power Plant," Directorate of Ucensing, issued February 1,1973.
24.
USAEC " Supplement 2 to the Safety Evaluation of the James A. FitzPatrick Nuclear Power Plant," Directorate of Ucensing, issued October 4,1974.
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.T STR I BUT I ON JAF NYO wpo R.
Liseno G. Goldstein J.C.
Brons W.
Fernandez R.E.
Beedle B.
Prucnal S.S.
Zulla W.V.
Childs J.A. Gray, Jr.
J.B.
Ellmers S.M. Toth E.A. Rodriguez S.
Rokerya J.A. Greene E.A.
Prus R.
Lauman L.
Guaquil G.M.
Wilverding A.
Klausmann Records Station 3243h
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